ML19354D586
| ML19354D586 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 10/26/1989 |
| From: | NEBRASKA PUBLIC POWER DISTRICT |
| To: | |
| Shared Package | |
| ML19354D583 | List: |
| References | |
| NUDOCS 8912280147 | |
| Download: ML19354D586 (309) | |
Text
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1 l 1 COOPER NUCLEAR STATION ; 1989 EVALUATED EEERCISE l TABLE OF CONTENTS Pace L PART I GENERAL INFORMATION .
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1.0 INTRODUCTION
1-1 2.0 SCOPE AND-OBJECTIVES 2-1 2.1 Scope 2-1 r 2.2 Onsite Objectives 2-1 2.3 Offsite Objectives 2-5 [ 3.0 EXERCISE INFORMATION 3-1 3.1 Conduct of the Exercise 3-1 3.2 Precautions and Limitations 3-2 3.3 Exercise Organization 3-4 4.0 CONTROLLER INFORMATION 4-1 4.1 General Information 4-1 4.2 controller Instructions 4-1 4.3 Evaluation Instructions 4-2 l 4.4 Personnel Assignments 4-2 5.0 PLAYER INFORMATION 5-1 5.1 General Information 5-1 5.2 Player Guidelines 5-1 6.0 SCHEDULE OF EVENTS 6-1
k COOPER NUCLEAR STATION 1989 EVALUATED EXERCISE l-TABLE OF CONTENTS , (Continued) PART II SCENARIO INFORMATION 7.0 SCENARIO J 7.1 Sequence of Events 7.2 Master Events Summary i 8.0 MESSAGES AND PLANT DATA l 9.0 RADIOCHEMISTRY SAMPLE AND RADIATION DATA 9.1 Radiochemistry Sample Data 9.2 Radiation Area Data l. 9.3 Process Monitor Data 10.0 METEOROLOGICAL AND RADIOLOGICAL RETRASE DATA 10.1 Radioactive Release Information 10.2 Meteorological Data f L- 10.3 Onsite Field Data 10.4 Offsite Field Data l- Plume Position Maps l 10.5
r 1 i 1 1 I l l l l I l l l i I i 1 l l l l i 1 . 1 l l SECTION 1.0 l l INTRODUCTION- l l 1 l l 1 l l l l l l; l l l l l l 1' l l l l
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COOPER NUCLEAR STATION 1989 EVALUATED EXERCISE
1.0 INTRODUCTION
The Cooper Nuclear Station Emergency Plan describes NPPD's capabilities to respond to a nuclear emergency at the Cooper Nuclear Station; with support from Federal, State, and local government agencies and private organizations. The CNS Emergency Plan provides for continuous emergency preparedness, including the conduct of an annual full-scale exercise. The purpose of the exercise is to activate and evaluate major portions of the emergency response organization and l- '~ facilities and other aspects of the Emergency Plan and associated Emergency Plan Implementing Procedures, in accordance with Nuclear Regulatory Commission (NRC) Regulation 10CFR50.47 (b) and Appendix E. The exercise is l conducted jointly with appropriate State and local agencies in order to assess State and local government emergency response plans, as required by Federal Emergency Management Agency (FEMA) Regulation 44CFR350.9(b). The conduct and evaluation of the exercise provides additional training for l
- emergency response organization personnel and a means to l further enhance Nebraska Public Power District's emergency l response capability.
This Exercise Manual has been developed to provide the basis for the conduct of an emergency exercise simulating a radiological accident at the Cooper Nuclear Station located l near Brownville in Nemaha County, Nebraska, through which the capabilities and effectiveness of the Emergency Response ! Plans for the Nebraska Public Power District, the states of i 1-1
1 COOPER NUCLEAR STATION 1989 RVALUATED EKERCISE Nebraska, and Missouri and their respective counties, can be evaluated. This manual is to be utilised by the controllers and. evaluators from the NPPD, the inspectors and evaluators from the NRC and FEMA, to initiate, control, and evaluate the activities of the participants in the exercise. This Exercise Manual consists of two parts. Part I provides a. general description and overview of an emergency exercise. Part II containa the scenario and time schedule of simulated plant conditions and is subject to a limited, controlled distribution. Exercise "clavers" will not have crior knowledae of the nature of the simulated incident or any carts thereof. l 1-2
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s l l SECTION 2.0 t 4 8 COPE AND OBJECTIVES 1 l l l l 1, b l l i-l-. I 1 l :' 1; l-I
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J COOPER NUCLEAR STATION 1989 EVALUATED EXERCKSE 2.0 BCOPE AND OBJECTIVES 2.1 SCOPE The Cooper Nuclear Station (CNS) 1989 Emergency' Exercisa Program is being conducted in order to test and evaluate Nebraska Public Power District's (NPPD) emergency plan and procedures. It will also test the emergency response organization's ability to assess and respond to emergency conditions and coordinate efforts with other agencies for protection of the health and safety of the public. The scenario will depict a simulated sequence of events, resulting in sufficiently degraded conditions to warrant the mobilization of NPPD, State and local l agencies to respond to the emergency. The Exercise l will have full participation by the NPPD emergency response organization and by the states of Nebraska and Missouri. Iowa and Kansas are not participating in the exercise. Whenever practical, the exercise will incorporate provisions for " free play" on the part of the participants. 2.2 ONSITE OBJECTIVES The Cooper Nuclear Station (CNS) 1989 Emergency Preparedness Exercise Program objectives are based on the Nuclear Regulatory Commission (NRC) requirements delineated in 10CFR50.47 and 10CFR50 Appendix E. Additional guidance provided in NUREG-0654, and FEMA- , 2 -1
e , COOPER NUCLEAR STATION 1989 EVALUATED EXERCISE REP-1 revision 1, NUREG-0696, and NUREG-0737 supple-ment i vas also utilized in developing these objectiven. The major objective of the exercise is to evaluate the integrated capability of a major portion of the basic elements existing within the onsite and offsite emergency plans and emergency response organizations. The specific objectives of the exercise to be demon-strated are listed below. control Room
- 1. Demonstrate proficiency in recognizing and classifying emergency conditions.
- 2. Domonstrate the activation of the Control Room as and Emergency Response Facility.
- 3. Demonstrate the operation of the Control Room as an Emergency Response Facility.
- 4. Demonstrate the effective use of emergency l
communications equipment. (IR 88-29)
- 5. Demonstrate the effective use of emergency procedures
! (EPIPs and EOPs). (IR 88-29)
- 6. Demonstrate initial notification of Federal, State, L
local, corporate, and station emergency personnel per l procedure 5.7.6. (IR 88-29) ! 7. Demonstrate the ability to maintain adequate logs in the Control Room. (IR 88-29)
- 8. Demonstrate the ability to follow procedures for repair i activities. (IR 88-29) i l
i 2-2
g COOPER NUCLEAR STATION 1989 EVALUATED EXERCISE I 1
- 9. Demonstrate the ability to communicate technical {
information between the Control Room and the Technical Support Center and the Emergency Operations Facility. (IR 88-29)
- 10. Demonstrate the ability to adequately turnover offsite communication responsibilities from the Control Room to the Technical Support center. (IR 88-29)
- 11. Demonstrate the ability to conduct initial accountability.
! 12. Demonstrate the ability to maintain accountability.
- 13. Demonstrate the ability to provide updated information to emergency response facility personnel. (IR 88-29)
- 14. Demonstrate the continuity of authority and transition l of responsibilities between emergency facilities as a result of escalating accident classification.
- 15. Demonstrate the ability to access radiological and meteorological data.
- 16. Demonstrate the ability to formulate a timely and accurate initial offsite radiological dose projection.
L l Technical suonort-Center
- 1. Demonstrate the activation of the Technical support Center.
- 2. Demonstrate the operation of the Technical Support Center.
- 3. Demonstrate the effective use of emergency communications equipment. (IR 88-29)
- 4. Demonstrate the effective use of emergency procedures (EPIPs and EOPs). (IR 88-29) 1 2-3 l
l
I I COOPER NUCLEAR STATION 1989 EVALUATED EXERCISE
- 5. Demonstrate follow-up notification of of fsite agencies per procedure. (IR 88-29)
- 6. Demonstrate the ability to maintain adequate logs in the Technical Support Center. (IR 88-29)
- 7. Demonstrate the ability to follow procedures for repair activities. (IR 88-29)
- 8. Demonstrate the ability to communicate technical information between the Technical Support Center and the Control Room and the Emergency Operations Facility.
(IR 88-29)
- 9. Demonstrate the ability to adequately turnover offsite communication responsibilities from the Technical Support Center to the Emergency Operations Facility.
(IR 88-29)
- 10. Demonstrate the ability to conduct initial accountability.
- 11. Demonstrate the ability to mainta!.n accountability.
- 12. Demonstrate the ability to assemble, brief, and track repair teams. (IR 88-29)
- 13. Demonstrate the ability to provide updated information to emergency response facility personnel. (IR 88-29)
- 14. Demonstrate the ability to trend events on facility status boards. (IR 87-25)
- 15. Demonstrate the continuity of authority and transition of responsibilities between emergency facilities as a result of escalating accident classification.
- 16. Demonstrate the mobilization of onsite radiological monitoring teams.
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1 COOPER NUCLEAR STATION 1989 EVALUATED EXERCI8E l
- 17. Demonstrate the proper use of equipment, procedures, and communications by the onsite radiological monitoring teams.
- 18. Demonstrate the ability to access radiological and meteorological data.
- 19. Demonstrate the ability to obtain, label, and analyze a sample utilizing the post-accident sampling system.
- 20. Demonstrate the ability to monitor and control emergency worker exposure within the station.
l 21. Demonstrate adequate equipment and procedures to monitor for contamination of emergency workers and l L equipment and to perform decontamination as required. l 22. Demonstrate the use of visual aids in the Technical Support Center. (IR 8'/-25)
- 23. Demonstrate the ability to respond to an accident involving a (simulated) contaminated injured worker. J (Dress Rehearsal only.)
I 24. Demonstrate the ability to evacuate non-essential I station personnel at a Site Area Emergency classification. )
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l. 1^ r l Emeraency opera +, ions racility l
- 1. Demonstrate the activation of the Emergency Operations Facility.
- 2. Demonstrate the operation of the Emergency Operations Facility.
- 3. Demonstrate the effective use of emergency communications equipment. (IR 88-29) l l'
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T F COOPER NUCLEAR STATION 1989 EVALUATED EXERCISE l
- 4. Demonstrate the effective use of emergency procedures (EPIPs and EOPs). (IR 88-29)
- 5. Demonstrate follow-up notification of offsite agencies per procedure. (IR 88-29)
- 6. Demonstrate the ability to maintain adequate logs in the Emergency Operations Facility. (IR 88-29)
- 7. Demonstrate the ability to communicate technical informatIonbetweentheEmergencyoperationsFacility and the Control Room and the Technical Support Center.
(IR 80-29)
- 8. Demonstrate the ability to adequately turnover offsite communication responsibilities to the Emergency Operations Facility from the Technical Support Center.
(IR 88-29)
- 9. Demonstrate the ability to conduct initial accountability.
- 10. Demonstrate the ability to maintain accountability.
- 11. Demonstrate the ability to provide updated information to emergency response facility personnel. (IR 38-29)
- 12. Demonstrate the ability to trend events on facility status boards. (IR 88-29)
- 13. Demonstrate the continuity of authority and transition or responsibilities between emergency facilities as a result of escalating accident classification.
- 14. Demonstrate the mobilization of offsite radiological monitoring teams.
- 15. Demonstrate the proper use of equipment, procedures, and communications by the offsite radiological monitoring teams.
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. t COOPER NUCLEAR STATION 1989 EVALUATED EXERCISE
- 16. Demonstrate the ability to access radiological and meteorological data.
- 17. Demonstrate the ability to continuously assess the impact of a release of radioactive materials to the .
environment.
- 18. Demonstrate- the ability to coordinate the available emergency response resources of NPPD, State and local organizations.
- 19. Demonstrate the ability of offsite radiological l' . monitoring teams to collect, label, and transport
! sample media.
- 20. Demonstrate the ability to analyze sample media from L
radiological monitoring teams. l 21. Demonstrate.-the ability to formulate and make protective action recommendations to protect station personnel and public based upon station conditions and/or field monitoring information.
- 22. Demonstrate the use of visual aids in the Emergency Operations Facility. (IR 88-29)
- 23. Demonstrate the ability to provide emergency I information to the General Office Emergency Center l (GOEC) and the Media Release Center (MRC). (IR 88-29) l 24.. Demonstrate decision-making rod coordination with offsite agencies in de-escalating and terminating the emergency.
- 25. Demonstrate decision-making and coordination with offsite agencies in planning re-entry to evacuated areas.
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_ _ _ . _ . . . . _ . . _ _ _ __ .__ m _ _ _ _ _ _. _ . _ _ _ . . l COOPER NUCLEAR STATION l 1989 ETALUATED EXERCISE
- 26. Demonstrate the ability to pir.n recovery operations and 1 identify the need for additionel resources. (This objective will be accomplished via tabletop and telephone conversations.)
itse une obinatives l
- 1. Demonstrate activation of the NPPD MRC (Personnel l
propositioned due to off-hours exercise). I l 2. Demonstrate set up of NPPD MRC work areas, equipment, 1 and materials.
- 3. Dertonstrate set up of " Media Briefing" area and equipment at the NPPD MRC (Board of Equalization Chamber of LC level will be utilized for briefings).
- 4. Demonstrate the capability to register NPFD, State, Federal, Media, and other personnel at the NPPD MRC.
- 5. Demonstrate the capability to provide CNS/NPPD background information to the Media at the NPPD MRC.
- 6. Demonstrate the capability to obtain current and accurate Gmergency information at the NPPD MRC.
- 7. Demonstrate the capability to coordinate and assemble emergency information for timely dissemination to the l public, via the media at the NPPD 'MRC (briefings, )
written statements). l
- 8. Demonstrate the use of visual aids during " media j briefings" at the NPPD MRC. )
9, Demonstrate the capability at the NPPD MRC to reply to l
- inquiries of both a technical and political nature i during " media briefings",. l
- 10. Demonstrate the capability at the NPPD MRC to respond )
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.____ . - -. _. . - - _ ~ - -.- _ - . . -_
i I COOPER NUCLEAR STATION 1989 EVALUATED REERCISE : i l r ! directly to questions from the Pablic (simulated) concerning real and rumored events occurring at CNS or ; within the 10 mile EPZ.
- 11. Demonstrate the capability to coordinate and plan Recovery operations with GCEC and CNS ERF personnel.
l 1989 GOEC Obiectives
- 1. Demonstrate activation of the NPPD GOEC (personnel prepositioned due to off-hours exercise). ,
- 2. Demonstrate set-up of NPPD GOEC, equipment, and materials.
- 3. Demonstrate the capability to obtain current and accuratu .mergency information at the NPPD GOEC.
- 4. Demonstrate the capability at the NPPD GOEC to coordinated and assemble emergency information for dissemination to the public prior to the MRC being declared operational, if necessary.
- 5. Demonstrate the capability, at the NPPD GOEC, to respond directly to questions from the Public (simulated) concerning real and rumored events occurring at CNS or within the 10 mile EPZ.
- 6. Demonstrate the capability, at the NPPD GOEC, to respond directly to questions from NPPD employees (simulated) concerning real and rumored events occurring at CNS or within the 10 mile EPZ.
- 7. Demonstrate the capability to coordinate and plan Recovery operations with MRC and CNS ERF personnel.
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i cooper NUCLEAR STATION 1989 EVALUATED REERCISE 2.3 oFFSITE OBJECTIVES i The following pages are duplicates of objectives submitted by the states of Nebraska and Missouri. . i 4 t i
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Jjy,Ag;rn STATE OF MISSOURI 1
' ' ""Jlf,fj*" {
- del'ARTMENT OF PUBLIC SAFETY OFFICE OF THE ADJUTANT GENERAL !
EMERGENCY MANAGEMENT AGENCY 9" l P. O. Box 116 ; Jefferson City, Missouri 65102 l ' I Phone 314 - 7519500 i July 27, 1989 l ( L Mr. Jerome D. Overstreet , Regional Director , FEMA _ Region VII 911 Walnut - Rm 200 Kansas City, MO 64106 , tear ~Mr. Overstreet: This letter is a supplement to the Missouri objectives matrix for -. the Cooper Nuclear Station exercise on October 25, 1989. The~ objective matrix is broken into two separata documents, the first contains the state objectives and the second, the Atchison . And Nodaway County objectives. L l ' The matrices are, for the most part, self-explanatory; but, I offer these comments to ensure that there are no misunderstand 1ngs, :
- 1. The year indicator in the block indicates which year that particular objective needs to be demonstrated. If the block contains a ayes" it means it will be demonstrated in 1989.
State objectives Matrix
- 2. Objective number 9 will be demonstrated this year.
Transport will be accomplished by courier in a car, i. so be aware that transportation time from the county EOC hours. to the RADLAB will take between four and five
- 3. Objective number 10 for alerting of Brickyard Hill Wildlife Area will be accomplished as outlined in the l ,
" Objectives Due Dates List" dated 19 April 1989. The mobile route alerting will be demonstrated by 1992.
The airplane will fly alerting on October 25 at approximately 10:00 a.m. ,
Page 2 4. Objective number 13 for the IAC. The IAC is staffed by Public Information personnel whose duties are to gather information and pass it on to the County PIO and the State PIO at the Media Release Center (MRC), if the MRC is activated. These individuals are not officials of Atchison county or the State of Missouri;.they can not accept official notification of an emergency from the utility.
- 5. objective number 28 for the RADLAB, will be demonstrated at the callawny exercise on october 11. The box is checked with a "yes" even though that objective will not be demonstrated unless there is problem at the Callaway exercise.
County Objectives
- 6. Under MEDICAL on objectives 4, 6, 16, 23 and 24, AMB.
means ambulance and HOSP means hospital. An AMB with ,
" backup" below it means back-up ambulance and the same is true for the hospital.
- 7. Demonstration of the objectives for medical will be out of sequence from the Cooper exercise. The demonstration will begin at approximately 1 00-1:30 p.m.
- 8. Demonstration of congregate care will also be out of sequence from the exercise.
This demonstration will take place at approximately 10:00 a.m. on October 25. ' 'Weathope up the these comments exercise. will alleviate any problems that may come Just one more note, you and your staff are to be commended for the l tracking and historical records you have been keeping. Coming up with the l like a very"Due Dates" arduous document must have looked at the beginning task. Thank you. Your staff did a very commendable job. If you have any questions, please contact Les Kampen of our of fice. l Sincera1y,. 4 Richard D. Ross LK:sb Enclosures - L '
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00PER STATE OBJECTIVES 1990 DA & IAC BYH EOC FCP FTC FM RL MRC WA Demonstrate the ability , to monitor, understand YES YES N/A N/A N/A YES YES N/A cnd use Emergency Class- ! ification Levels (ECL) through the appropri-cte implementation . Of emergency functions cnd activities cor-responding to ECL ' cs required by the scenario. The four ECL's are: Notification of Unusual Event, Alert, Site Area l Emergency and General
- Emergency. (New)
Demonstrate the ability YES YES YES 1993 N/A 1993 YES l to fully alert, mobil- N/A l ize and activate per-l sonnel for both facil-ity and field-based t cmargency functions.(1) - Demonstrate the ability l to direct, coordinate YES YES YES N/A N/A N/A N/A N/A cnd control emergency cctivities. Demonstrate the ability to communicate with all YES YES YES YES N/A YES YES cppropriate locations, N/A organizations, and , field personnel. (5) Demonstrate the ade-quacy of facilities YES YES YES N/A N/A YES YES N/A cquipment, displays cnd other materials to support emergency operations.(4)
*" Core objectives" that are to be demonstrated in each biennial cxercise.
PAGE 1
1 l l l l 1 EDC FCP DA&FTC RL FM MRC IAC BYH WA . 1 Demonstrate ability N/A YES YES N/A YES N/A YES YES to continuously monitor cnd control emer worker exposure.gency (20)
?. Demonstrate the appro- N/A N/A N/A N/A YES priate equipment and -
N/A N/A N/A procedures for deter- ' oining field radia- ' tion r.easurements. (7)
- 1. Demonstrate the appro- N/A N/A N/A N/A YES N/A
' priate equipment and N/A N/A' procedures for the ceasurement of airborne radiciodine concentra- ,
tions as low as 10" oicrocurie per cc in the presence of noble gases. (8)
- n. Demonstrate ability to
' N/A N/A N/A YES YES N/A N/A N/A cbtain samples of parti-culate activity in the
- cirborna plume and promptly perform labora-tory analyses. (New)*
- 0. Demonstrate the ability within the plume exposure N/A N/A YES N/A N/A N/A pathway, to project dosa- N/A N/A cge to the public via j plume exposure based on plant and field data.
(10)
*" Core objectives" that are to be demonstrated in each biennial oxercise.
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EOC FC DA&FTC RL FM MRC IAC BYH WA
- 1. Demonstrate the ability to make appropriate N/A N/A JES N/A N/A N/A N/A protective actions N/A decisions, based on ,
l projected or actual ' dosage. EPA PAG's ~ cva11 ability of cdequate shelter, - - - - : -. cvacuation time ~ Cstimates and other t relevant factors (10)
- 2. Demonstrate the ability N/A N/A 'N/A N/A N/A N/A N/A YES to initially alert the public within the 10 cile EPZ, and begin '
dissemination of an instructional message within 15 minutes of , a decision by appro-priate State and/or , local official (s). (13)
- 3. Demonstrate the ability N/A N/A N/A N/A N/A N/A YES N/A to coordinate the form-ulation and dissemin-
- ction of accurate in-formation and instruc-tions to the public in o timely fashion after the initial alert and notification has cccurred. (14, 25)
- 4. Demonstrate the ability to brief the media in N/A N/A N/A N/A N/A YES N/A on accurate, coordinate N/A cnd timely manner. (24)
- 5. Demonstrate the ability to establish and oper- N/A N/A N/A N/A N/A N/A N/A N/A ate rumor control in o coordinated and timely fashion. (26)
*" Core objectives" that are to be demonstrated in each biennial exercise.
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i 4 EOC FCP DA&FTC RL FM MRC IAC BRY WA
- 6. Demonstrate the ability 0 to make the decision to N/A 1991 1991 N/A 1991 N/A 1991 YES recommend the use of KI to emergency workers cnd institutional 2 zed '
persons, based on pre- , determined criteria, cs well as to distri-
- bute and administer
- it once the decision '
is made, i f necessi-tated by radiciodine ' releases. (21, 22)
- 7 Demonstrate the ability N/A N/A N/A N/A N/A N/A N/A N/A to make the_ decision ,
if the state plan co specifies, to recommend the~use of KI for the general
- public, based on i predetermined cri-l teria, as well as l to distribute and
? -cnd administer it
- l once the decision is made, if necessi-tated by radiciodine releases. (21, 22)
- 8. Demonstrate the ability N/A N/A N/A N/A N/A N/A N/A N/A
'* .cnd resources necessary to implement appropri- 5 cte protective actions for the impacted perm-cnent and transient L plume EPZ population l (including transit-dependent persons, cpecial needs popu-lations, handicapped cnd institutionalized persons). (15)
** " SCENARIO Dependent PAGE 4
l EOC FCP DA&FTC RL TM NRC IAC BYH WA
- 9. Demonstrate the ability N/A N/A N/A N/A
'o N/A N/A N/A N/A and resources necessary to implement appropriate !
protective actions for I school children within the pluma EP2. (19) L:0. Demonstrate the organi- N/A N/A N/A N/A N/A N/x'N/A N/A I zational ability and I resources necessary to i control evacuation traffic flow and to control access to ovacuated and shel-tered areas. (16,17) ti . Demonstrate the ade-quacy of procedures, N/A N/A N/A N/A N/A N/A N/A N/A J facilities, equipment und personnel for the registration, radio-logical monitoring and decontamination of evacuees. (27)
!2. Demonstrate the ade- "* quacy of facilities, N/A N/A N/A N/A N/A N/A N/A N/A equipment and person-nel for congregate care of evacuees. (28) l3. Demonstrate the ada-no quacy of vehicles, N/A N/A N/A N/A N/A N/A N/A N/A equipment, procedures and personnel for transporting contam-inated, injured or exposed individuals.
(31)
** Scenario Dependent PAGE 5
EOC FCP DA & RL TM NRC IAC BYH TTC WA
- 24. . Demonstrate the ade- N/A N/A N/A N/A N/A N/A N/A N/A
'o quacy of medical faci-lities equipment, pro-cedures, personnel for handling contaminated ,
injured or exposed
- individuals. (31).
- 15. Demonstrate the ade-
'8 quacy of facilities, N/A N/A N/A N/A N/A N/A N/A N/A equipment, supplies, procedures and per-sonnel for decon-tamination of emer- .
gancy workers, equip-ment and vehicles and for. waste disposal. (29)
!6. Demonstrate ability 1991 1991 N/A N/A N/A N/A N/A N/A '* to identify the need for and call upon '
federal and other outside support agencies assistance. (32) i
!7. Demonstrate the appro- <* priate use of equip- N/A N/A N/A N/A N/A 1992 N/A N/A ment and procedures ,
for collection and l transport of samples l of vegetation, food crops, milk, meat, poultry, water, and animal feeds (indi-genous to the area and stored). (9), i
** Scenario Dependent PAGE 6
l l 1 EOC FCP DA&FTC RL FM MRC IAC BYH WA '8. Demonstrate the appro-d- priate lab operations ! N/A N/A N/A 1992 N/A N/A N/A N/A and procedures for ' taasuring and analy-zing samples of vegetation, food i crops, milk, meat, poultry, water and - i cnimal feeds (indi-genous to the area , cnd stored). (9)
- 19. Demonstrate the ability N/A N/A NO
<* N/A N/A N/A N/A N/A to project dosage to public for ingestion , pathway exposure and determine appropriate , protective measures, based on field data, FDA PAG's and other relevant factors. (11)
- 10. Demonstrate the ability
<* to implement both pre- N/A 1991 N/A N/A N/A N/A N/A N/A ventive and emergency
- protective actions for ingestion pathway hazards. (12) 11 . Demonstrate the ability PEND-to estimate total pop- N/A N/A ING N/A N/A N/A N/A
- ulation exposure. (34) N/A GUID-ANCE FROM FEMA
- 12. Demonstrate the ability '
- to determine appropri- N/A 1991 N/A N/A N/A N/A N/A N/A ate measures for con-trolled re-entry and recovery based on ostimated total pop-ulation exposure, cva11able EPA PAG's cnd other relevant factors. (35)
** Scenario Dependent PAGE 7
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- __.____m_ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ -
i 1 i I i EOC FCP DA&TTC RL FM MRC IAC BHY WA
- 13. Demonstrate ability to N/A 1991 N/A N/A N/A N/A N/A N/A
'* implement appropriate ceasures for controlled re-entry and recovery.
(35) 14 . Demonstrate the ability 1991 1992 1991
'o-YES YES 1993 1991 N/A i to maintain staffing cn a continuous 24 hour basis by actual shift change. (2)
- 15. Demonstrate the ability N/A N/A N/A
'o N/A N/A N/A N/A N/A to coordinate the evac-untion of on-site par-Connel. (23) .
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- 16. Demonstrate the ability ;
<* to carry out emergency YES YES YES N/A YES YES YES N/A response EOC's, mobil-12e staff that report to the EOC's, establish communications linkages cnd complete telephone '
call down during an unannounced off hours drill or exercise. (New)
** Scenario Dependent L
1 l l 1 l PAGE 8
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'OOPER COUNTY OBJECTIVES 1990 ATCHISON NODAWAY ,
EW MEDICAL SCHOOL l RECPT. CON. CARE EOC DECON CTR. Demonstrate the ability ' to monitor, understand Cnd use Emergency Class- YES N/A N/A N/A N/A N/A ification Levels (ECL) , through the appropri- . Ote implementation
- of emergency functions cnd' activities cor-responding to ECL as required by the scenario. The four ECL's are: Notification
! cf Unusual Event, l Alert, Site Area . Emergency and General ! Emergency. (New) l !. Demonstrate the ability to fully alert, mobil- YES 1992 N/A 1992 N/A YES l 1re and activate per-sonnel for both facil-ity and field-based cmergency functions.(1) '
.. Demonstrate the ability to direct, coordinate YES N/A N/A N/A 1992 YES Cnd control emergency activities.
L.- Demonstrate the ability to communicate with all YES 1992 1991 YES 1992 YES appropriate locations, (AMB) organizations, and 1993 field personnel. (5) (BACKUP) Demonstrate the ade-quacy of facilities YES N/A N/A N/A N/A N/A cquipment, displays cnd other materials to support emergency operations.(4)
'" Core objectives" that are to be demonstrated in each biennial Oxercise.
PAGE 1
9 L ATCHISON ,NODAWAY EOC EW MEDICAL SCHOOL R&C CTR CON. CARE DECON l
- 6. 1991 Demonstrate ability (AMB) to continuously monitor YES 1992 1993 YES and control emer 1992 N/A worker exposure.gency BACKUP (2) 1994 HOSP '
1992 BU . 7 0 Demonstrate the appro-priate equipment and N/A ' procedures for deter- N/A N/A N/A N/A N/A mining field radia-tion measurements. (7)
- 8. Demonstrate the appro-o priate equipment and N/A procedures for the N/A N/A N/A N/A N/A measurement of airborne radiciodine concentra-tions as low as 10*'
microcuria per cc in th presence of noble gases (8)
- 9. Demonstrate ability to l obtain samples of parti N/A N/A N/A culate activity in the N/A N/A N/A airborne plume and promptly perform labora-tory analyses. (New)*
! 10. Demonstrate the ability Within the plume exposur pathway, to project dosa N/A N/A N/A N/A N/A NA/ age to the public via plume exposure based on plant and field data. (10)
*" Core objectives" that are to be demonstrated in each biennial cxercise.
l PAGE 2
t l ATCHISON NODAWAY EOC EW NEDICAL SCHOOL DECON - R&C CTR CON. CARE
'11. Demonstrate the ability to make appropriate N/A protective actions N/A N/A N/A N/A N/A decisions, based on i
projected or actual dosage. EPA PAG's ' availability of adequate shelter, evacuation time , estimates and other relevant factors.(10) '
'2.
Demonstrate the ability to initially alert the YES public within the 10 N/A N/A N/A N/A N/A
- mile EPZ, and begin dissemination of an instructional message within 15 minutes of a decision by appro-priate State and/or local official (s).
(13) ,
- 3. Demonstrate the ability to coordinate the form- YES N/A N/A ulation and dissemin- N/A' N/A N/A i
Otton of accurate in-formation and instruc-tions to the public in o timely fashion after , the initial alert and j notification has u eccurred. (14, 25)
- 4. Demonstrate the ability to brief the media in N/A N/A N/A cn accurate, coordinate N/A N/A N/A cnd timely manner. (24) l *" exercise.
Core objectives" that are to be demonstrated in each biennial PAGE 3 g 93 0
l l ATCHISON NODAWAY EOC .EW MEDICAL SCHOOL lDECON l$Rirc l CTR'[ CON] l S. Demonstrate the ability l to establish and oper- YES N/A N/A N/A N/A N/A i ote rumor control in o coordinated and timely fashion. (26) .
- 6. Demonstrate the ability to to make the decision to 1991 N/A 1991-AMB YES N/A N/A ,
recommend the use of 1993- ' KI to emergency workers BACKUP cnd institutionalized persons, based on pre- . determined criteria, , os well as to distri-bute and administer 1 it once the decision is made, if ne:essi-tated by radiciodine releases. (21, 22)
- 7. .-Demonstrate the ability *
- to make the decision N/A N/A N/A N/A- N/A N/A !
if the State plan co specifies, to recommend the use of KI for the general
.public, based on predetermined cri-teria, as well as to distribute and and administer it once the decision is made, if necessi-tated by radiciodine releases. (21, 22)
* " Core Objectives" that are to be demonstrated in each biennal exercise.
** " SCENARIO Dependent PAGE 4 e
me 4 8 =
,,.,.,y_.,,_ __. , _ _ . , . . . - . . . _ _ _ . _ . . _ - _ . _ _ , .
f- .
}
ATCHISON NODAWAY EOC EW NEDICAL SCHOOL R&C CTR CON. CARE I DECON l l l
- 8. Demonstrate the ability
-o cnd resources necessary 1992 N/A N/A N/A N/A N/A to implement appropri-ate protective actions for the impacted pern-cnent and transient .
plume EPE population (including transit-dependent persons, cpecial needs popu-lations, handicapped , cnd institutionalized persons). (15)
- 9. Demonstrate the ability
- o Cnd resources necessary 1991 N/A N/A YES N/A N/A to implement appropriate protective actions for ochool children within the pluma EPZ. (19)
'O. Demonstrate the organi-
- zational ability and 1993 N/A N/A N/A N/A -
N/A
- resources necessary to l control evacuation traffic flow and to I
control access to I evacuated and shel-l tered areas. (16,17)
!1. Demonstrate the ade-
-to quacy of procedures, N/A N/A N/A N/A 1992 N/A facilities, equipment and personnel for the .
registration, radio-logical monitoring and decontamination of evacuees. (27)
- 12. Demonstrate the ade-
** quacy of facilities, N/A N/A N/A N/A N/A YES equipment and person-l nel for congregate care of evacuees. (28)
** SCENARIO DEPENDENT PAGE 5 l
. i t
i r ATCHISON NODAWAY EOC EW NEDICAL SCHOOL R&C CTR CON. CARE DECON , . ,,,
- 23. Demonstrate the ade-
'O quacy of vehicles, N/A N/A 1991 N/A NO N/A cquipment, procedures AMB cnd personnel for 1993 transporting contam- BACKUP inated, injured or Cxposed individuals.
(31) 14 . Demonstrate the ade-
'# quacy of medical faci N/A N/A 1994 N/A NO N/A lities equipment, pro HOSP cedures, personnel fo 1992 handling contaminated BACKUP injured or exposed individuals. (31).
- 15. Demonstrate the ade-
~'o quacy of facilities, 1992 N/A N/A N/A N/A N/A equipment, supplies, .
procedures and per-connel for decon- - tamination of emer-gency. workers, equip-Cent and vehicles and for waste disposal. , (29) -
- 16. Demonstrata ability
'o to identify the need l N/A N/A N/A N/A N/A N/A
- for and call upon ,
L federal and other ' ! outside support cgencias assistance. (32)
** SCENARIO DEPENDENT PAGE 6 i
.......L.-..... ... ..
I . 5 - "*h,,
._y,~~T.i,-
ATCHISON .? t NODAWAY EOC EW . ' MEDICAL SCHOOL R8rc CTR CON.CAREf DECON
- 7. Demonstrate the approa o priate use of equip-ment and procedures N/A N/A" 'N/A ,
N/A N/A N/A for collection and transport of samples -- ---.n -- of vegetation, food crops, milk, meat, ' poultry, water, and animal feeds (indi- ' genous to the area and stored). (9). *' l
'8. Demonstrate the appro-
- priate lab operations N/A N/A N/A N/A N/A N/A and procedures for L ,
measuring and analy-zing samples of vegetation, food crops, milk, meat, poultry, water and , animal feeds (indi- , I genous to the area and stored). (9) .
- 9. Demonstrate the ability
'* to project dosage to N/A N/A N/A , N/A N/A N/A public for ingestion L pathway exposure and .
determine appropriate , protective measures, c' based on field data, - FDA PAG's and other relevant factors. (11) .
;0. Demonstrate the ability .
l
'* to implement both pre- NO N/A N/A N/A N/A N/A ventive and emergency protective actions for ingestion pathway hazards. (12) ,
j.
't. Demonstrate the ability
- to estimate total pop- N/A N/A N/A N/A N/A N/A ulation exposure. (34) .
** SCENARIO DEPENDENT PAGE 7
.._..-,_:u..... . . . -
I
'a [
ATCNISON NODAWAY l EOC EW MEDICAL SCHOOL R&d CTR CON. CARE DECON '
- 2. Demonstrate the ability 4' '
to determine appropri- 1991 N/A N/A N/A N/A N/A cte measures for con-trolle6 re-entry and recovery based on Catinated total pop- ! ulation exposure, - cvailable EPA PAG's cnd other relevant factors. (35) 13 . Demonstrate ability to 1991 N/A N/A N/A N/A N/A
- implement appropriate i censures for controlled re-entry and recovery. ,
(35) 14 . Demonstrate the ability
'* to maintain staffing YES 1992 N/A N/A 1991 YES cn a continuous 24 hour basis by actual shift change. (2) l L5. Demonstrate the ability l '* to coordinate the evac- N/A N/A N/A N/A N/A N/A l
uation of on-site per-l connel. (23)
- 2 L '. 6 . Demonstrate the ability
'a to carry out emergency YES N/A N/A N/A N/A N/A response EOC's, mobil-ize staff that report I to the EOC's, establish I
communications linkages I cnd complete telephone-call down during an unannounced off hours l drill or exercise. L (NEW) l
** SCENARIO DEPENDENT l
PAGE 8
- _. . . . ~ . . - . . .. . . . . _ ~ . .
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SECTION 3.0 1 I EXERCISE INFORMATION l l l l
l COOPER NUCLEAR STATION 1989 EVALUATED EXERCISE i 3.0 EXERCISE INFORMATION : l 3.1 CONDUCT OF TEE EEERCISE s
. The exercise will simulate an abnormal radiological incident at the Cooper Nuclear Station. The effec-tiveness of selected organizations, personnel and functions of the appropriate Emergency Plans and Implementing Procedures will be demonstrated. The ,
simulated emergency will then terminate. The Recovery Phase will be initiated, and the Exercise will then be terminated. Emergency response actions during the simulated emergency will include: o recognition and classification of emergency con-ditions o assessment of onsite/offsite radiological con-sequences o alert / notification and mobilization of emergency response organizations o implementation of in-plant corrective actions o activation / operation of emergency response facilities and equipment 3-1
j' I COOPER NUCLEAR STATION 1989 EVALUATED EXERCISE o preparation of reports, messages, and record keeping ; o recommendation of protective actions, and ter . mination of the emergency condition and limited , i recovery /re-entry discussions point for The Control Room will be the central ; distribution of exercise messages and is the key to ensuring that the exercise progresses on schedule. Simulated plant parameters and annunciators will be > provided to the Control Room operators using message forms and plant data sheets. A wide variety of plant ; information is provided so that at no time will the , messages prompt the players or provide undue assistance in recognition of events. Information available on SPDS will also be provided in the TSC and the EOF where output consoles are located. Contingency messages (denoted by an 'x' after the message number) are delivered only when conditions described in the controller notes have been met. Radiological and meteorological data presented in Sections 9.0 and 10.0 and information included in the supplemental scenarios will be disseminated by con-trollers when players demonstrate the capability to obtain the information from appropriate sources. At , no time, unless noted specifically as an exception, i will information be interjected at a point where it would not be available in a real emergency. The Lead 3-2 1
~
4 f COOPER NUCLEAR STATION : 1989 EVALUATED EXERCISE Controllers may interject other information or change ! a message to ensure that the exercise progresses as planned. The exercise Players are expected to " free play" the ; scenario to the extent practical. If corrective , actionn are postulatwd that would terminate the emergency, they should be identified to the Lead Controller in the affected facility, so that the 4 scenario will progress as designed. Notifications of, and contact with, supt tvisors, plant management, and offsite agencies will be made in accordance with the , Emergency Plan Implementing Procedures. No simulations P are to be allowed unless specifically noted in the Exercise Manual or directed by a Controller for , scenario purposes. ! 3.2 PRECAUTIONS AND LIMITATIONS This section provides information for all exercise participants related to the rules and guidelines to be followed throughout the conduct of this Exercise. Prior to initiation of the exercise, a pre-exercise briefing will be held to review the entire exercise process with all the exercise controllers and observers. o should, at any time during the course of the conduct of this exercise, an actual emergency situation arise, all activities and communications 3-3 v- -
l
)
COOPER NUCiLEAR STATION 1989 EVALUATED EXERCISE , related to the exercise will be suspended. It will be the responsibility of any exercise controller ' or observer that becomes aware of an actual emergency to suspend exercise response in his/her o immediate area and tt. inform the Lead Exercise ' Controller of the situation. Upcn notification of an actual emergency, the Lead Exercise Controller may notify all other controllers to suspend all > exercise activities. o Should, at any time during the course of the conduct of this exercise, an exercise controller l or observer witness an exercise participant undertake any action which would, in the opinion of the Controllar, place either an individual or ( component in an unsafe condition, the Controller is responsible for intervening in the individual's actions and terminating the unsafe activity immediately, o- No response to an exercise situation will be simulated without Controller approval. No action will be taken that reduces the margin of safety in the plant. I o All repair activities associated with the scenario l will be simulated with extreme caution emphasized ! around operating equipment. Manipulation of any plant operating systems, valves, breakers, or controls in response to this exercise is to be 3-4
.... I l
l COOPER NUCLEAR STATION 1989 EVALUATED EEERCISE , simulated. There is to be no alteration of any i plant operating equipment, systems, or circuits , during the response of this exercise. No ; pressurization of fire hoses, discharging of fire : extinguishers, or initiation of any fire suppression systems will be allowed for the exercise. o All telephone communications, radio trans-missions, and public address announcements related to the Exercise must begin and and with the statement, "This is a drill". Should a controller witness a drill participant not observing this practice, it ' is the controller's responsibility to remind the individual of the need to follow this procedure. l J o Any motor vehicle response to this Ex6rcise, whether it be ambulance, fire fighting equip-ment, police / security vehicles or field monitoring teams, should observe all normal motor vehicle operating laws including posted speed limits, stop lights / signs, one way streets, etc. Red lights and sirens will not be operated on emergency vehicles for the purposes of the Exercise. o Care must be taken to assure that any non-participating individuals who may observe exercise activities or overhear exercise communications are not misled into believing that an actual emergency exists. Any exercise controller who is aware of I 3-5
I l COOPER NUCLEAR STATION ! 1989 EVALUATED EXERCISE ! an individual or group of individuals in the immediate vicinity who may have become alarmed or confused about the situation, should approach that ! individual or group and explain the nature of the exercise and its intent. i i 3.3 EXERCISE ORGANISATION The organization for this exercime will consist of the Exarcise Coordinator, the Lead Exercise Controller, the controllers, the Evaluators, the Observers, and the Players as follows: 3.3.1 The Exercise coordinator is responsible for the post exercise Controller debriefing, the CNS exercise critique and the NRC critique and exit meeting. Subsequent to the exercise, he will direct the preparation of a consolidated evaluation package and preparation of an itemized list of recommended corrective actions. 3.3.2 The Lead Exercise Controller is responsible for the conduct of a successful exercise and will coordinate exercise preparations in-cluding the development of the scenario and messages. The Lead Exercise Controller will ensure the safe conduct of the exercise and is responsible for resolution of any scenario-related inter-f acility questions, as well as 3- 6
4 ..
- f-COOPER NUCLEAR STATION 1989 EVALUATED EXERCI8E the assurance that the ccnduct of the exercise does not adversely impact the operation of the station. The Lead Exercise Controller will 1
also coordinate the preparation of a consolidated evaluation package. 3.3.3 The Controllers are qualified personnel selected to perform functions as follows: A. A Lead Controller is assigned to each emergency response facility. The Lead Controller is responsible for all Controller, Evaluator, and Observer activities for that facility and, as appropriate, its associated teams. Controllers for teams or sub-areas of a facility report to the Lead controller of that facility. B. Controllers will delive;; " Exercise Messages" to designated players at specified times and places during the exercise, inject or deliver contingency messages as required to prompt the appropriate player response and keep the exercise actions moving according to the scenario, observe the exercise at other assigned locations, and prepare an evaluation. Controllers will submit written recommendations to the Lead 3-7
x COOPER NUCLEAR STATION 1989 EVALUATED EXERCIBE controller, who will summarize all comments for submittal to the Exercise Coordinator. The Controllers are provided with instructions and evaluation forms in Section 4.0 of this manual. 3.3.4 Evaluators are personnel who are assigned to judge the effectiveness of participating organizations, personnel, and activities in response to the scenario. They will evaluate performance on the basis of standards or requirements contained in the appropriate Emergency Plan, Implementing Procedures, Exercise messages, and as described herein. 3.3.5 Observers may be authorized, on a limited basis, to participate in the exercise for the purpose of observing exercise activity for personal educations. 3.3.6 Insoectors are members of the NRC or FEMA evaluation teams and will have prior knowledge of the exercise scenario. At their assigned locations they will observe the exercise and prepare an evaluation to be presented at the exit meeting and critique. 3.3.7 Players include station and other utility personnel assigned to perform emergency functions as described in the Emergency Plan 3-8 '
c-I COOPER NUCLEAR STATION 1989 EVALUATED EXERCISE and Implementing Procedures.- Players from offsite organizations and agencies (county, State, and private industry) are participants in the exercise as described in their respective emergency plans and standard operating procedures.
~3-9
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i i i l 1 l i l l i 1 l \c l i. rt I a l l l l l 1 i 1 l l l l l l SECTION 4.0 -1 l I l i CONTROLLER INFORMATION l I 1 i l I l' 1 l i i i 1 i i l l I
COOPER NUCLEAR STATION 1989 EVALUATED EXERCISE 4.0 CONTROLLER INFORMATION 4.1 GENERAL INFORMATION Each Controller should be familiar with the following: i o The basic objectives of the exercise (Section 2.0) . o The assumptions and precautions being taken (Section 3.0).- - o The exercise scenario, including the initiating events and the. expected course of action to be taken (Section 7.0). o The various locations that will be involved and the specific items to be oeserved at those locations. I u o The evaluation checklists provided.- 4.2 CONTROLLER INSTRUCTIONS o controllers will position themselves at their l assigned locations 30 minutes prior to the activation of the facility or team for which they (. have responsibility. 1 o Cominunications will be tested prior to exercise commencement. All watches and clocks will be l I 4-1 :
4 COOPER NUCLEAR STATION 1989 EVALUATED EXERCISE synchronized with the Control Room clock as part of the cormunications testing. o All controllers will comply with instructions from-the Lead Exercise Controller. o Each Controller will have copies of the messages controlling the progress of the exercise scenario. No messages shall be delivered out of sequence or other than as written unless specifically authorized by the Lead Exercise Controller. b o Controllers will not provide information to the' Players regarding scenario progression or reso-lution of problems encountered in the course of 1 the simulated emergency. The exercise parti-l- cipants are expected to obtain information through l their own organizations and exercise their own judgement in determining response actions and l resolving problems. l o Some Players may insist that certain parts of the scenario are unrealistic. The Controllers have the sole authority to clarify any questions regarding scenario content.
- 4.3 EVALUATION INSTRUCTIONS Each Controller will take detailed notes regarding the progress of the exercise and response of the exercise 4-2
COOPER NUCLEAR STATION 1989 EVALitATED EXERCISE participants at their assigned locations. Each controller should carefully note the arrival and departure times of participants, the times when major activities or milestones occur, and problem areas encountered. Controllers' comments will be used for the purpose of reconstructing the Exercise chronology and preparing a written evaluation of the exercise. Emergency Response Facility checklists are taken from Attachment E of the Surveillance Procedure 6.3.11.1 of
.the CNS operations Manual. These checklists must be completed by each Controller and Evaluator and provided to the Exercise Coordinator at the conclusion of the exercise. Controller evaluation ' forms for each facility / team will be distributed at the pre-exercise controller briefing.
4.4 PERSONNEL ASSIGNMENTS The Personnel assignments for the Controller organization are as follows: Control Room (LATER) Technical Succort Center (LATER) 4-3 v
.i V
1 COOPER NUCLEAR STATION
.- 1989 EVALUATED EXERCISE Ooerational Suonert Centers (LATER)
In-Plant (recort to TSC) . i (LATER) Emercency Ooerations Facility (LATER) Downwind Survev Teams (LATER) General Office Emeraency Center (LATER) l Media Release Center i (LATER) 4-4
t
- f. , :~t SECTION 5.0 PLAYER INFORMATION I
~...
COOPER NUCLEAR-STATION 1989 EVALUATED REERCISE 5.0 PLAYER INFORMATION 5.1 GENERAL INFORMATION This section provides information for all exercise Players. These guidelines should be followed throughout the conduct of-the Exercise. A pre-exercise briefing will be held for key players to review the entire exercise process, including " Precautions and Limitations" in Section 3.2, and the following information. The success of the exercise is largely dependent on player performance. Appropriate reaction to simulated emergency conditions and demonstrated . competence in the Emergency Plan and Implementing Procedures are the key criteria by which the players are evaluated. It is imperative, therefore, that all player actions and activities are witnessed by a controller. Any actions that are to be simulated must be brought to ' the attention of the Controller to ensure that credit is awarded. The success of the exercise is based on the demonstration of the predetermined exercise objectives. 5.2. PLAYER GUIDELINES o Maintain a serious attitude throughout the exercise. o Maintain courtesy and professionalism at all times. 5-1 l i
4 COOPER NUCLEAR STATION 1989 EVALUATED EXERCISE o Teamwork is essential! Do your job and then help other people do theirs. For example, if you know certain information should be available, ask for it . -- This makes you look good and may reduce a deficiency for someone else. o Think! Brainstorm and look for all possible solutions or consequences of events. Maintain the
" big picture" of what is happening, o Identify yourself by name and function to the Controller in your area. Always wear your identification badge, o If you are entering normal- nuclear station radiation areas, observe all rules and procedures.
No one (including Controllers) is exempt from
. normal station radiological practices and procedures.
NOTE: DO NOT ENTER HIGH RADIATION AREAS IN THE PLANT; FOLLOW ALARA PRINCIPLES. o observe all normal security procedures. All normal security procedures are in effect without exception. If a security condition arises, obey immediately the directions of Security Guards. o Elements of exercise play will be introduced through use of controlled exercise messages and by m.
n COOPER NUCLEAR STATION 1989 EVALUATED EEERCISE information generated by Players as a result of a particular emergency activity performed. Therefore, be responsible for initiating actions in accordance with instructions and responsibilities. o Communications should be concise and formal with use of abbreviations minimized. Always include "This is a drill". o Use and demonstrate knowledge of the Emergency Plan and Implementing Procedures. o No response to an exercise situation will be simulated without controller approval. No action will be taken that reduces the margin of safety in the-plant. o Keep a list of items which you believe will improve the plan'and/or procedures. Provide this to your Controller / Evaluator at the end of the Exercise. o Remember, one of the main purposes of an exercise is for you to assure yourself that you are adequately prepared. Areas for improvement or lessons learned, when identified, will improve your overall emergency preparedness. 5-3
' - I ti iii il
Z (_ SECTION 6.0 SCHEDULE OF EVENTS
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COOPER NUCLEAR STATION 1989 EVALUATED EXERCISE Date 2133 Event Location Particinants-4 (LATER) t .- l. l l 5-4 ,
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SECTION 8.0 MESSAGES AND PLANT DATA
- ~ .. - _. . .. . . . - - .- -_
COOPER NUCLEAR STATION 1989 EVALVATED EXERCISE EVALUATED EXERCISE SCENARIO SEQUENCE OF EVENTS 4
' Actual Scenario Summary Time Time 1745 -00/15 INITIAL CONDITIONS
- The reactor is at 100% power and has been operating for 40 weeks.
The core is near the and of core , life.and has been exposed for 256 full power days.
- Drywell identified leakage is 2.0 gpm. Drywell unidentified leakage is 0.5 gpm and has been steady for the past two weeks.
- HPCI full flow test per Surveillance Procedure 6.3.3.1 is due and scheduled for 1815 this evening. "B" RHR is operating in suppression pool cooling mode in preparation for this test. Similarly, "B" SBGT is in service for the test.
- Maintenance is working various, routine, low priority MWRs in a management effort to reduce the MWR backlog.
- The grid is stable.
- The weather forecast for this evening is for calm winds at 3-5 MPH out of the south. Skies .
are expected to be partly cloudy with only a 10% chance of J precipitation. Low temperatures are expected to be in the upper 40s.
- All other plant systems are operable and in their normal configuration.
Actual Scenario Summary Time ~ Time 1800 00/00 Initial conditions are established. Commence the Cooper Nuclear Station 1989 Evaluated Exercise. i 1815 00/15 HPCI has ruptured between the HPCI turbine stop valve and control valve (in the HPCI Room) . The HPCI primary containment isolation valves fail to close, and cannot be closed by remote or local operation. The HPCI rupture is, however, effectively isolated by the autoritic closure of the HPCI turbine stsp valve. ALERT An ALERT should be declared per EPIP 5.7.1, Attachment B, page 9 of 23, Initiating Condition 2.2.2.C.1,
" Inability to isolate Primary Containment".
'1830 '00/30 Operators commence a controlled shutdown as required by T.S. Action Statement 3.7.D.3 due to the f ailure of the HPCI primary containment isolation valves.
1930 01/30 A jumper left in a panel during troubleshooting of the RPT indicating lights becomes loose and inadvertantly shorts terminals that causes a trip of both recirculation pump generator field breakers. This causes an immediate loss of the recirculation pumps without coastdown. Undampened power oscillation begin almost immediately as the reactor is in the unstable region of the power / flow map. Clad damage is postulated to occur.
'1933 01/33 Concurrent with operator actions to manually scram the reactor, an MSIV closure due to 3 X Normal Main Steam Line High Radiation occurs.
All control rods fully insert, and the containment isolation in response
I s 1
-l Actual Scenario Summary Time Time l l
l l to this event is successful, except 1 for the AOG Steam Supply Isolation j Valves MO-920 and MO-921 which fail ! to close. SRVs cycle on high pressure, but the electrical functioning of the SRVs is lost due to an electrical failure. , 1945 01/45 Radiation monitors at the ERP show elevated levels. SITE AREA EMERGENCY A SITE AREA EMERGENCY should be declared per EPIP 5.7.1, Attachment L B, page 7 of 23, Initiating Condition 1.3.2., " Radiological gaseous effluent releases resulting in l THYROID dose Iata at the site i boundary of 250 Mrem /hr as determined I by ADAM, DOSE, hand calculations, or in-field surveys". 1945 01/45. The RCIC turbine trips due to a spurious overspeed signal. RCIC is rendered inoperable for the remainder l of the scenario, when the overspeed L trip mechanism is discovered to be non-repairable. Level initially drops but is then maintained when CRD
- l. flow is maximized.
2030 02/30 The steam jet air ejector steam supply line ruptures in the ARW building. ARW ventilation picks up this contaminated steam and discharges it to the environment via the ARW Building Ventilation. The release is now considered a ground level, unfiltered, monitored release. GENERAL EMERGENCY A GENEPAL EMERGENCY should be declared per EPIP 5.7.1, Attachment B, page 7 of 23, Initiating Condition 1.4.2., " Radiological gaseous effluent releases resulting in THYROID dose rate at the site boundary of 5 Rem /hr using actual
I I l Actual- Scenario Summary Time Time Met. conditions as determined by i ADAM, DOSE, hand calculations, or in- 1 field surveys". l 2115 03/15 I&C restoreo half of the SRVs to electrical operability. The operating crew performs an emergency depressurization of the reactor per the EOPs. The release is essentially . terminated. 2130 03/30 Repair teams successfully isolate HPCI by closing the inboard steamline isolation valve. This action restores primary containment. 2200 04/00 Operators place the shutdown cooling mode of RHR in service. 2230 04/30 The plume is dispersed out of the 10 mile EPZ. The reactor is placed in a stable, cold shutdown condition. . Downgrade / termination discussions are in progress. 2245 04/45 Offsite doses are returned to background. A Recovery organization is established. Recovery planning is initiated, with long term organization and response plans formulated. 2300 05/00 The 1989 Cooper Nuclear Station Evaluated Exercise is terminated.
l 1989 EVALUATED EXERCISE Time m -00/15 i Message Number I.C. t= 1745 COOPER NUCLEAR STATION 1 EMERGENCY PREPAREDNESS EXERCISE MESSAGE i i l Message for Control Room ' I simulated Plant Conditions: See attached Plant Data Messages
***THIS IS A DRILL ***
Initial Conditions are established as follows: l o The reactor is at 100% power and has been operating l continuously for 40 weeks. The core is near the end of L -core life and has been exposed for 256 full power days. o Drywell identified leakage is 2.0 gpm. Drywell unidentified leakeage is 0.5 gpm and has been steady for the past two weeks. I o HPCI full flow test per Surveillance procedure 6.3.3.1-is due and scheduled for .1815 this evening. "B" RHR is L operating in-suppression pool cooling mode in preparation for this test. Similarly, "B" SBGT is in service for the test. i o Maintenance is working various, routine, low priority MNRs l in a management effort.to reduce the MWR backlog. MWRs being worked include trouble shooting of the Emergency Bearing Oil Pump, RFPT low suction pressure instruments, and ARI-RPT indicating. lights, o The grid is stable. o The weather forecast for this evening is for calm winds at 3-5 MPH out of the south. Skies are expected to be partly cloudy with only a 10% chance of precipitation. Low temperatures are expected to be in the upper 40s. o All other plant systems are operable and in their normal operating configuration. l
1989 RVALUATED EXERCISE Time a 1745 MESSAGE NUMBER I.C. ta -00/15 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE FOR CONTROLLER USE ONLY: Controller Informations o Deliver Initial Conditions to the Control Room drill team. Explain abbreviations and acronyms, go through data and ensure that all players understand the initial conditions. o Conduct a pre-drill briefing. Explain that any player dispatched in the plant must go to the TSC to pick up a controller, o Discuss the rules for conduct of the drill, and simulatiens allowed during the drill. o Ensure controller clock synchronization occurs. o Ensure a Station Operator is dispatched to the HPCI Room. Expected Acticus: ! o Read and understand the initial conditions. l [ o Dispatch a Station Operator to the HPCI Room for the HPCI l surveillance test. l 1 1 I' l
1989 EVALUATED EXERCISE Time a 1745-Message Numbert I.C. t s -00/15 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE PLANT DATA PANEL 9-1 PANEL 9-5 STATUS PRESS (psig) FLOW (gpm) REACTOR POWER 100 % APRM ! RHR A STBY 50 0 REACTOR LEVEL 35 " NR RHR C STBY 50 REACTOR PRESSURE 1000 (psig) RHR B SPC 240 7700 ELQH (los lbs/hr) RHR D STBY 50 FEEDWATER A 4.8 CS A STBY , 50 0 FEEDWATER B 4.8
-CS B STBY '50 0 MAIN STEAM A 2.4 i HPCI. STBY 50 0 MAIN STEAM B _221_
L Drywell Pressure 0,25 (psig) MAIN STEAM C 2.4 Torus Level 1221 (feet) MAIN STEAM D 2.4
- OPEN CLOSED CRD A FLOW 50 (gpm)
MSIV' 8 0 CRD B FLOW 0 (gpm) 1; SLC LEVEL 75 % PANEL 9-4 SLC PMP DISCH PRESS A 0 SLC PMP DISCH PRESS B 0 STATUS PRESS (psig) ELQH(gpm) RCIC AVAIL 50 0 ; L RWCU A OPER 1180 160 MISCELLANEOUS PANELS RWCU B AVAIL 0 0 RRP A 100 % SPD DIESEL GEN 1 STBY RRP B 100 % SPD DIESEL GEN 2 STBY SBGT A STBY ; i SBGT B OPER DRYWELL COOLING OPER TORUS WATER TEMP 80 9F DRYWELL TEMP 110 T
COOPER NUCLEAR STATION RADIATION MONITORS 1989. EVALUATED EXERCISE CLOCK TIME a 1745 8CENARIO TIME = -00/15 STATION. DESCRIPTION READING (mR/hr) 1 Rx Bldg Fuel Pool Area (SE 5th Floor) 154 2 Rx Bldg Fuel Pool Area (SE 5th Floor) 1.5 3 Rx Bldg New Fuel Area (SE 5th Floor) 0.3 4 Rx Bldg Rx Water Cleanup Domineralizer 113 Area (SW 3rd Floor)
'5 Rx Bldg Sludge and Jecarit Pump Area 0.8 (S 2nd Floor) 6 Rx Bldg Neutron Monitor System Index 164 Area (TIP Room 1st Floor)-
7 Rx Bldg Neutron Monitor System Drive 1.8 Mech Area (SE 1st Floor) 8 Rx Bldg Control Rod Hydraulic Equipment 0.9
~ Area (S ist Floor) 9 Rx Bldg Control Rod Hydraulic Equipment 9 Area-(N ist Floor) 10 , Rx Bldg HPCI Pump Room (SW Quad) 0.3 11 Rx Bldg RHR Pump Room (SW Quad) 5 12 Rx Bldg RHR Pump Room (NW Quad) 24 13 Rx Bldg RCIC/CS Pump Room (NE Quad) 2 14 Rx Bldg CSLPump Room (SE Quad) 5 3
15 Turbine Bldg Turbine Front Standard 131 L 16 Turbine Bldg Mezz Control Corridor 0.2 l 17 Turbine Bldg Basement Control Corridor .05 : L 18 Turbine Bldg Rx Feed Pump Area 6 19 Turbine-Bldg Condensate Pump Area .12 20 Control Room Main Control Room .02 21 Grade Level Control Corridor .19 22 Radwaste Control Room .03 23 Radwaste Pump Room 5 24 Radwaste Basement Equipment Area 4 25 Radwaste Demineralizer Valve Room 1.2 26 Radwaste Conveyor Aisle Operating Area 0.2 27 SPARE 28 Radwaste Lab Area .01 29 Centrifuge East 10 30 Centrifuge West 9 Panel 9-02 Personnel Airlock Area 903' 12 R/hr Panel 9-02 Ladder 903' to 2nd Level 7 R/hr OSH = Offscale High
. ._ ~ ~ - - . . . _ _ _ - . . .
COOPER NUCLEAR-STATION RADIATION NONITORS 1989 EVALUATED EXERCISE CLOCK TIME a 1745 SCENARIO TIME a -00/15
..........=.........................................................u.=
PANEL VBDG s Rx Bldg Vent Eff (RMV-RM-40) 1.0E-3 uCi/sec ERP Stack Normal Eff (RMP-RM-3A) 5.5E-1 uCi/sec ERP Stack High Range (RMP-RM-3B) 0 uCi/see Turbine Bldg Vent Eff (RMV-RM-20A) 1. SE-3 uCi/sec Turbine Bldg High Range (RMV-RM-20B) o uCi/sec RW/ARW Bldg Combined Eff (RMV-RM-30A) 1.5E-3 uCi/sec RW/ARW Bldg High Range (RMV-RM-30B) o uCi/see 1 PANEL 9-10 Main Steam Rad Monitor Ch. A1, B1 350 mR/hr 350 mR/hr Ch. A2, B2 300 mR/hr 270 mR/hr SJAE Off Gas Log Rad Monitor Ch. A, B 35 mR/hr 25 mR/hr Rx Bldg Vent Ind/ Trip Unit Ch. A, B O.6 mR/hr 0.6 mR/hr l l I l l i.. L I t
- - - - m
1989 EVALUATED EXERCISE Tirse = 1800 Message Number: 1 t= 00/00 COOPER NUCLEAR STATION i EMERGENCY PREPAREDNESS EXERCISE MESSAGE Messaae for: Control Room Simulated Plant Conditiong: See attached Plant Data Message:
***THIS IS A DRILL ***
Make the following PA announcement:
" Attention all personnel. We are now commencing the CNS 1989 Emergency Preparedness Evaluated Exercise. All announcements prefaced by 'This is a drill' are intended for designated drill participants only. If an actual incident occurs, an announcement will be made directing response to the emergency situation."
l (Repeat once) (
c l- b. , 1989 EVALUATED EXERCISE Time = 1800 PISSAGE NUMBER: _1_ t= 00/00 > CQQfER NUCLEAR STATION EMERGENCY. PREPARED 1?ESS EXERCISE MESSAGE FOR CONTROf.TFR USE ONLY: controller Informations o Ensure that'the PA announcement is made. . o See Supplemental Scenario No. 1 which starts at 1815. Ensure a Station operator is dispatched to the HPCI Room. Erpected Actions: l l 9 4 - -
b , 1989 EVALUATED EEERCISE Time a 1800 Wessage Number _1_ t= 00/00 j COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS REERCISE PLANT DATA PANEL 9-3 PANEL 9-5 STATUS PRESS (psig) ELQH(gpm) REACTOR POWER 100 % AEEM RHR A STBY 50 0 REACTOR LEVEL 35 " _HE_ ; RHR C STBY 50 REACTOR PRESSURE 1000 (psig) 6 RHR B SPC 240 7700 E1QH (10 lbs/hr) RHR D STBY 50 FEEDWATER A 4.8 CS A STBY 50 0 FEEDWATER B 4.8 CS B STBY 50 0 __ MAIN STEAM A 2.4 HPCI STBY 50 0 MAI?I STEAM B 2.4 Drywell Pressure 2225 (Psig) MAIN STEAM C 2.4 Torus Level 1221 (feet) MAIN STEAM D 2.4 QEEH CLOSED CRD A FLOW 50_ (gpm) MSIV 8 0 CRD B FLOW 0 (gpm) SLC LEVEL 75 % PANEL 9-4 SLC PMP DISCH PRESS A 0 l SLC PMP DISCH PRESS B 0 STATUS PRESS (psig) ELQE(gpm) l RCIC AVAIL 50 0 RWCU A OPER 1180 160 MISCELLANEOUS PANELS RWCU B AVAIL 0 0 RRP A 100 % SPD DIESEL GEN 1 STBY RRP B 100 % SPD DIESEI GEN 2 STBY SBGT A STBY SBGT B OPER DRYWELL COOLING OPER TORUS WATER TEMP 80 9P DRYWELL TEMP 110 9P
1989 EVAll!ATED EXERCISE Time = _l500 Message: 1 COOPER NUCITAR STATION t= 00/00 EMERGENCY PREPAREDNESS EXERCISE SPDS DATA , teactor Power ( Avg 1 FRM) teactor Levet (in.)
+150 120
+100 100
+50 80 ';
O 60 50 40 , 100 20 150 0 , 30 15 0 30 15 0 teactor Pressure (psig) 1200 1000 800 600 400 200 0 30 15 0 OrWelt Pressure (psig) Orwell ferversture (Of ) 300 75 250 60 200 45 150 30 100 15 50 0 0 30 15 0 30 15 0 locus Level (in.) forus Water Tenperature ('F)
+?4 300 250
+12 200 0 150 100
-12 50 24 O 30 15 0 30 15 0
, ~~~'
l 1989 EVALUATED EXERCISE Time = 1815 l Message Numbert 2 tn 00/15_ COOPER NUCLEAR STATION EMERGENCY PREPAREDNES8 EXERCISE MESSAGE Message fort control Room simulated Plant conditionst See attached Plant Data Messaget
*** TRIS IS A DRILL ***
During step 8.2.14 of procedure 6.3.3.1, the following alarms annunciate in the Control Room: HPCI ISOLATION SIGNAL 14GIC A/B INITIATED PNL 9-3-2/2-3 HPCI STEAM LINE DIFFERENTIAL PRESSURE HIGH PNL 9-3-2/5-2 HPCI TURBINE TRIPPED PNL 9-3-2/1-1 . HPCI-MO-15 OR MO-16 NOT FULLY OPEN PNL 9-3-2/2-2 , HIGH AREA TEMPERATURE PNL 9-3-3/2-3 HPCI VALVES MOTOR OVERIDADED PNL 9-3-2/6-3 Indications in the Control Room includet . HPCI inboard steam supply isolation valve, MO-15, red light stays lit, grean light does not illuminate. HPCI outboard steam supply isolation valve, MO-16, red and green lights both illuminated for 3 seconds, then both are extinguished. HPCI valves MO-58, AOV-A070, AOV-A071, and MO-25 all go closed. HPCI turbine stop and control valves both go closed. HPCI pump room area temperature is 162*F and decreasing. I
C00PER NUCLEAR STATION ! RADIATION MONITORS t 1989 EVALUATED REERCISE CLOCK TIME a 1800 I SCENARIO TIME = 00/00 l STATION DESCRIPTION READING (mR/hr) 1 Rx Bldg Fuel Pool Area (SE 5th Floor) 154 2 Rx Bldg Fuel Pool Area (SE Sth Floor) 1.5 3 Rx Bldg New Fuel Area (SE Sth Floor) 0.3 _ 4 Rx Bldg Rx Water Cleanup Domineralizar 113 Area (SW 3rd Floor) 5 Rx Bldg Sludge and Decant Pump Area 0.8 ; (S 2nd Floor) 6 Rx Bldg Neutron Monitor system Index 164 Area (TIP Room ist Floor) 1 7 Rx Bldg Neutron Monitor System Drive 1.8 Mech Area (SE lat Floor) 8 Rx Bldg Control Rod Hydraulic Equipment 0.9 Area (S ist Floor) 9 Rx Bldg Control Rod Hydraulic Equipment 9 Area (N ist Floor) 10 Rx Bldg HPCI Pump Room (SW Quad) 0.3 , 11 Rx Bldg RHR Pump Room (SW Quad) 5 12 Rx Bldg RHR Pump Room (NW Quad) 24 13 Rx Bldg RCIC/CS Pump Room (NE Quad) 2 14 Rx Bldg CS Pump Room (SE Quad) 5 i 15 Turbine Bldg Turbine Front Standard 131 l 16 Turbine Bldg Mezz Control Corridor 0.2 17 Turbine Bldg Basement Control Corridor .05 18 Turbine Bldg Rx Feed Pump Area 6 19 Turbine Bldg Condensate Pump Area .12 20 Control Room Main Control Room .02 21 Grade Level Control Corridor .19 22 Radwaste control Room .03 23 Radwaste Pump Room 5 24 Radwaste Basement Equipment Area 4 25 Radwaste Domineralizer Valve Room 1.2 26 Radwasta Conveyor hisle Operating Area 0.2 27 SPARE 28 Radwaste Lab Area .01 29 Centrifuge East 10 30 Centrifuge West 9 Panel 9-02 Personnel Airlock Area 903' 12 R/hr Panel 9-02 Ladder 903 ' to 2nd Level 7 R/hr OSH = Offscale High
I COOPER NUCLEAR STATION RADIATION MONITORS 1989 EVALUATED EXERCISE CLOCK TIME a 1800 SCENARIO TIME a 00/00 PANEL VBDG Rx Bldg Vent Eff (RMV-RM-40) 1.0E-3 uCi/see ERP Stack Normal Eff (RMP-RM-3A) 5.5E-1 uCi/see ERP Stack High Range (RMP-RM-3 B) o uCi/see Turbine Bldg Vent Eff (RMV-RM-20A) 1.5E-3 uCi/see Turbine Bldg High Range (RMV-RM-20B) o uci/see RW/ARW Bldg Combined Eff (RMV-RM-30A) 1.5E-3 uCi/see RW/ARW Bldg High Range (RMV-RM-30B) o uCi/see PANEL 9-10 Main Steam Rad Monitor Ch. A1, B1 350 mR/hr 350 mR/hr Ch. A2, B2 300 mR/hr 270 mR/hr SJAE off Gas Log Rad Monitor Ch. A, B 35 mR/hr 25 mR/hr Rx Bldg Vent Ind/ Trip Unit Ch. A, B 0.6 mR/hr 0.6 mR/hr
. , . . _ . _ _ . _ _ ________.________._______m
i
)
l i l 1989 EVAIDATED EXERCISE Time = 1815 j i MESSAGE NUMBER: 1 t= 00/15 l COOPER NUCLEAR STATIOJ l EMERGENCY PREPAREDNESS EXERCISE MESSAGE , i FOR CONTROT.TRR USE ONLY! Controller Information: o see supplemental Scenario Number 1. HPCI has ruptured in the HPCI Room and the HPCI isolation valves have failed to close. The rupture is isolated, however, by the closure of the HPCI stop valve. Expected Actions: o Perform actions in the Annunciator Response Procedures and enter EOP-3. o Evacuate the area of the HPCI Room, o Investigate the f ailure of the HPCI isolation valves. Attempt to close the HPCI isolation valves, o Enter T.S. Action Statement 3.7.D.3 due to failure of the HPCI primary containment isolation valves. Commence an orderly shutdown and place the reactor in cold shutdown with 24 hours, o Shift Supervisor declare an ALERT in accordance with EPIP 5.7.1, Attachment B, page 9 of 23, Initiating Condition 2.2.2.C.1, " Inability to isolate Primary Containment". I o Shift Supervisor implement EPIP 5.7.3, " ALERT". o Shitt Supervisor assume duties as the Emergency Director and implement EPIP 5.7. 6, " Notification", EPIP 5.7.7, " Activation of TSC", EPIP 5.7.8, " Activation of OSCs", and EPIP 5.7.10,
" Personnel Assembly and Accountabily".
i 1989 EVALUATED EXERCISE Time a 1815-Mossage Numbert _1_ t= 00/15 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE PLANT DATA .
?
PANEL 9-3 PANEL 9-5 STATUS PRESS (psig) ELQH(gpm) REACTOR POWER 100 % AEEM RHR A STBY 50 0 REACTOR LEVEL 35 " _HE_ RHR C STBY 50 REACTOR PRESSURE 1000 (psig) 8 RHR B SPC 240 7700 FLOW (10 lbs/h>) RHR D STBY 50 FEEDWATER A 4.8 CS A STBY 50 0 TEEDWATER B 4.8 CS B STBY 50 0 MAIN STEAM A 2.4 HPCI TRIPPED 50 0 MAIN STEAM B 2.4 I Drywell Pressure pali (psig) MAIN STEAM C 2.4 Torus Level 1121 (feet) MAIN STEAM D 2.4 QEEH CLOSED CRD A FLOW 50 (gpm) MSIV 8 0 CRD B FLOW 0 (gpm) SLC LEVEL 75 % PANEL 9-4 SLC PMP DISCH PRESS A 0 SLC PMP DISCH PRESS B 0 3,IAIME PRESS (psig) ELQH(gpm) RCIC AVAIL 50 0 RWCU A OPER_ 1180 160 MISCELLANEOUS PANELS RWCU B AVAIL 0 0 RRP A 100 % SPD DIESEL GEN 1 STBY RRP B 100 % SPD DIESEL GEN 2 __STBY SBGT A STBY SBGT B OPER DRYWELL COOLING OPER TORUS WATER TEMP 80 9P DRYWELL TEMP 110 9F
n l 1989 EVALUATED EXERCISE Time = J$l5 Message: 2 COOPER NUCIIAR STATION t = _0 0 /00 EMERGENCY PREPAREDNESS EXERCISE SPDS DATA teactor Power ( Avg 1 APRM) seector Levet (in.) 120
+100 100
+50
; 80 60 50 ,
40 ;
, 100 i ! 20 -
150 0 30 15 0 30 15 0 teactor Pressure (psig) 1200 1000 800 600 400 l 200 o 30 15 0 i Drywell Pressure (psty) Drywell Tenperature (Of ) ! 300 j 75 250 60 l 200 45 l 150 ! 30 15 I 50 j 0 ,
- 0 30 15 0 30 15 0 i f orus Level (in.) Torus Veter Tenperature (DF )
+24 300 I
250
+12 200 0 150 100 12 l 50 i.
-24 0 30 15 0 30 15 0 l
l
l COOPER NUCLEAR STATION RADIATION MONITORS 1989 EVALUATED EXERCISE CLOCK TIME a 1815 SCENARIO TIME = 00/15
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STATION DESCRIPTION READING (mR/hr) 1 Rx Bldg Fuel Pool Area (SE 5th Floor) 154 2 Rx Bldg Fuel Pool Area (SE 5th Floor) 1.5 3 Rx Bldg New Fuel Area (SE 5th Floor) 0.3 4 Rx Bldg Rx Water Cleanup Domineralizer 113 Area (SW 3rd Floor) 5 Rx Bldg Sludge and Decant Pump Area 0.8 . (S 2nd Floor) 6 Rx Bldg Neutron Monitor System Index 164 Area (TIP Room 1st Floor) ' 7 Rx Bldg Neutron Monitor System Drive 1.8 Mech Area (SE 1st Floor) 8 Rx Bldg Control Rod Hydraulic Eguipment 0.9 Area (S 1st Floor) 9 Rx Bldg Control Rod Hydraulic Equipment 9 Area (N 1st Floor) 10 Rx Bldg HPCI Pump Room (SW Quad) 5 11 Rx Bldg RHR Pump Room (SW Quad) 5 12 Rx Bldg RHR Pump Room (NW Quad) 24 13 Rx Bldg RCIC/CS Purp Room (NE Quad) 2 14 Rx Bldg CS Pump Room (SE Quad) 5 15 Turbine Bldg Turbine Front Standard 131 16 Turbine Bldg Mezz Control Corridor 0.2 17 Turbine Bldg Basement Control Corridor .05 18 Turbine Bldg Rx Feed Pump Area 6 19 Turbine Bldg Condensate Pump Area .12 20 Control Room Main Control Room .02 21 Grade Level Control Corridor .19 l 22 Radwaste Control Room .03 23 Radwaste Pump Room 5 . . . . 24 Radwaste Basement Equipment Area 4 12 5 Radwaste Demineralizer Valve Room 1.2 26 Radwaste Conveyor Aisle Operating Area 0.2 27 SPARE 28 Radwaste Lab Area .01 29 Centrifuge East 10 30 Centrifuge West 9 l Panel 9-02 Personnel Airlock Area 903' 12 R/hr Panel 9-02 Ladder 903' to 2nd Level 7 R/hr OSH = Offscale High l _ * - _ .e. . ' . .. - -
U ! I COOPER NUCLEAR STATION l RADIATION MONITORS 1989 EVALUATED EXERCISE CLOCK TIME a 1815 8CENARIO TIME a 00/15 i PANEL VBDG > Rx Bldg Vent Eff (RMV-RM-40) 1.0E-3 uCi/sec ERP Stack Normal Eff (RMP-RM-3A) 5.5E-1 uCi/sec. ERP Stack High Range (RMP-RM-3B) o uCi/see Turbine Bldg Vent Eff (RMV-RM-20A) 1.5E-3 uCi/sec Turbine Bldg High Range (RMV-RM-20B) o uC1/see RW/ARW Bldg Combined Eff (RMV-RM-30A) 1.5E-3 uCi/sec RW/ARW Bldg High Range (RMV-RM-30B) 0 uci/sec PANEL 9-10 Main Steam Rad Monitor Ch. A1, B1 350 mR/hr 350 mR/hr Ch. A2, B2 300 mR/hr 270 mR/hr l SJAE off Gas Log Rad Monitor Ch. A, B 35 mR/hr 25 mR/hr Rx Bldg Vent Ind/ Trip Unit Ch. A, B O.6 mR/hr 0.6 mR/hr r A q. . , . _,
**49*
. . _ . _ _ _ .. -. ~ . - _ _ - . - .
l 1989 EVALUATED EXERCISE Time = *1830 Message Number 2.1X t = '00/30 j r COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE Messaae fort Shift Supervisor simulated Plant conditions: Messaget
***THIS I8 A DRILL ***
Declare an ALERT in accordance with EPIP 5.7.1, Attachment B, page 9 of 23, Initiating Condition 2.2.2.C.1, " Inability to Isolate Primary Containment".
I I 1989 EVALUATED EXERCISE Time =
- 1830 !
MESSAGE NUMBER: 2.1X t= 30/1 ! COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE i FOR CONTROTTFR USE ONLY: Controller Information: o Deliver this message only if an ALERT has not been declared, and if there are no discussions in progress that will result in the declaration of an ALERT. Erpacted Actions: o See Message No. 2 " Expected Actions". t t r I f a C e e+pp
I 1989 EVALUATED EXERCISE Time a '1830 Message Number 2.2I tu *00/30 SQEFER.ELQhEAR_3TATION i EMERGENCY PREPAREDNESS EXERCISE MESSAGE ! Message fort Control Room ainulated Plant Conditions e Messages
*** TRIS IS A DRILL ***
Commence an orderly shutdown in accordance with Technical Specification 3.7.D.3. t t t b l l l l- [
I-l- EVALUATED EXERCISE Time = '1830 MESSAGE NUMBER: 2.2X t= '00/30 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE FOR.. CONTROLLER ..USE ONLY: Controller Information: o Deliver this message only if a controlled shutdown required by the T.S. Action statement 3.7.3.D has not been commenced, and if there are no discuwsions in progress that will result in the commencement of an orderly plant shutdown. Expected Actions: o comply with the message and initiate an orderly shutdown.
l f 1989 EVALUATED EXERCISE Time = *1830 t Message Numbert 2.3X t = *00/30 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE t Message _ fort Control Room Simulated Plant Conditions: Messages
*** TRIS IS A DRILLe**
The load dispatcher reports that Gentleman just tripped and spin reserve is extremely low. He requests that CNS remain above 90% power for approximately 1 hour while he arranges for start up of system peaking stations. l l l 4 e e
I I 1989 EVALUATED EXERCISE Time = '1830 f MESSAGE NUMBER: 2.3X t= "00/30 i i COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE FOR CONTROLLER USE ONLY: Controller Informations o Deliver this message verbally when operators notify the load dispatcher of the impending plant shutdown, o If operators commence shutdown without notifying the load dispatcher, intercede as the load dispatcher and ask why Cooper's power output is decreasing. Lead the conversation - to reactor shutdown rate constraints of the cover sheet.
- i Expected Actionst o comply with the request.
4 b
+
- - 9- 9 ,,% .. ...e..- e
r i L 1989 EVAIDATED EXERCISE Time = 1830 i Message Number: 3 t= 00/30 QQQPER NUCLEAR STATION : EMERGENCY PREPAREDNESS EXERCISE MESSAGE : i Message for: Control Room Simulated Plant Conditions: See attached Plant Data Message: '
* * *TtIIS IS A DRILL * *
- i b
I 1 I-
l 1 1989 EVALUATED EXERCISE Time = 1830 MESSAGE NUMBER: 3 t= 00/30 COOPER NUCLEAR ST&I1QM EMERGENCY PREPAREDNESS EXERCISE MESSAGE FOR CONTROLLER USE ONLYt Controller Informations o Adjust data sheets if operators have commenced their controlled shutdown. o Adjust "B" RHR status if operators decide to secure Suppression Pool Cooling since HPCI is no longer operating. It will not be necessary to adjust torus water temperature as it is postulated that the cooling water is at 80F also. Similarly, adjust SBGT if operators decide to place it back to a standby condition. Expected Actions L t i l _ _ ., a_ . ,- ,- -_,-
l 1 1 l 1989 EVALUATED EXERCISE Time a _1830 ; i Nessage Numbert )_. t= 00/30 i COOPER NUCLEAR STATION ! EMERGENCY PREPAREDNESS EXERCISE PLANT DATA I l PANEL 9-3 PANEL 9-5 STATUS PRESS (psig) ELQH(gpm) REACTOR POWER 100 % APRM RHR A STBY_ 50 0 REACTOR LEVEL 35 " _EE_ l RHR C STBY 50 REACTOR PRESSURE 1000 (psig) RHR B SPC 240 7700 ELQH s (lo lbs/hr) RHR D STBY 50 TEEDWATER A 4.8 ' CS A STBY 50 0 FEEDWATER B 4.8 CS B STBY 50 0 MAIN STEAM A 2.4 HPCI TRIPPED 50 0 MAIN STEAM B 2.4 Drywell Pressure 0.25 (psig) MAIN STEAM C 2.4 Torus Level 12.8 (feet) MAIN STEAM D 2.4 QEEH CLOSED CRD A FLOW 50 (gpm) MSIV 8 0 CRD B FLOW 0 (gpm) SLC LEVN, 75 % PANEL 9-4 SLC PMP DISCH PRESS A 0 SLC PMP DISCH PRESS B 0 STATUS PRESS (psig) ELQW(gpm) ___ RCIC AVAIL 50 0 RWCU A OPER 1180 160 MISCELLANEOUS PANELS RWCU B AVAIL 0 0 RRP A 100 % SPD DIESEL GEN 1 STBY RRP B 100 % SPD DIESEL GEN 2 STBY SBGT A STBY SBGT B __OPER DRYWELL COOL 7NG OPER TORUS WATER T.:MP 80 9F DRYWELL TEMP 110 _F* I
- h. 4 - __m.. . , . - . - -, _ . . - - _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ . _ _ - - - - _ _ _ -
a 1989 CVALUATED EXERCISE Time = _ i B 30 Message: 3 COOPER NUCLEAR STATION t= 00/30 EMERGENCY PREPAREDNESS EXERCISE SPDS DATA Feactor Power ( Avg % APRM) teactor Level (In.)
+150 120 ,
+100 100 i
+50 80 0
60 50 40 100 - 20 l 150 0 30 15 0 30 15 0 Reactor Pressu e (psig) 1200 1000 8 30 i l 600 l 400 l 200 0 30 15 0 Drw ell Pressure (psig) Drywell Tecperature ('F )
)
300 l D l 250 200 45 150 30 100 15 50 0 0 30 15 ) 30 15 0 f orus Level (in.) Torus b'ater f enperature ('F)
*24 300 250
+12 200
- 0 1$0 1
100 l all 50 ( 24 ' 0 ! 30 13 0 30 15 0 l 3 . _ _ _ . _ - _ __-_____m - __ _ _ & ,
I I
)
COOPER NUCLEAR STATION RADIATION MONITORS 1989 EVALUATED EEERCISE CLOCK TIME = 1830 SCENARIO TIME = 00/30 ; STATION DESCRIPTION READING (mR/hr) . 1 Rx Bldg Fuel Pool Area (SE 5th Floor) 154 ' 2 Rx Bldg Fuel Pool Area (SE 5th Floor) 1.5 3 Rx Bldg New Fuel Area (SE 5th Floor) 0.3 4 Rx Bldg Rx Water Cleanup Domineralizer 113 5 Area (SW 3rd Floor) ' Rx Bldg Sludge and Decant Pump Area 0.8 ' (S 2nd Floor) 6 Rx Bldg Neutron Monitor System Index 164 ' Area (TIP Room ist Floor) 7 Rx Bldg Neutron Monitor System Drive 1.8 8 Mech Area (SE 1st Floor) Rx Bldg Control Rod Hydraulic Equipment 0.9 9 Area (S ist Floor) Rx Bldg Control Rod Hydraulic Equipment 9 10 Area (N 1st Floor) Rx Bldg HPCI Pump Room (SW Quad) 5 11 Rx Bldg RHR Pump Room (SW Quad) 5 12 Rx Bldg RHR Pump Room (NW Quad) 24 13 Rx Bldg RCIC/CS Pump Room (NC Quad) 2 14 Rx Bldg CS Pump Room (SE Quad) 5 15 Turbine Bldg Turbine Front Standard 131 16 Turbine Bldg Mezz Control Corridor 0.2 17 Turbine Bldg Basement Control Corridor .05 18 Turbine Bldg Rx Feed Pump Area 6 1 19 Turbine Bldg Condensate Pump Area .12 20 Control Room Main Control Room .02 21 Grade Level Control Corridor .19
- 22 Radwaste Control Room
.03
- 23 Radwaste Pump Room 5 24 Radwaste Basement Equipment Area 4 25 Radwaste Domineralizar Valve Room 1.2 26 Radwaste Conveyor Aisle Operating Area 0.2 27 SPARE 28- Radwaste Lab Area .01 29 Centrifuge East 10 30 Centrifuge West 9 Panel 9-02 Personnel Airlock Area 903' 12 R/hr Panel 9-02 Ladder 903' to 2nd Level 7 R/hr i
OSH = Offscale High
COOPER NUCLEAR STATICW RADIATION MONITORS 1989 EVALUATED EXERCISE CLOCK TIME a 1830 SCENARIO TIME a 00/30 '
=======================================================================
PANEL VBDG Rx Bldg Vent Eff (RMV-RM-40) 1.0E-3 uCi/see ERP Stack Normal Eff (RMP-RM-3A) 5.5E-1 uCi/sec ERP Stack High Range (RMP-RM-3B) 0 uCi/see Turbine Bldg Vent Eff (RMV-RM-20A) 1.SE-3 uCi/see Turbine Bldg High Range (RMV-RM"20B) 0 uCi/see RW/ARW Bldg Combined Eff (RMV-RM-30A) 1.SE-3 uC1/see RW/ARW Bldg High Range (RMV-RM-30B) o uCi/see PANEL 9-1Q Main Steam Rad Monitor Ch. A1, B1 _350 mR/hr 350 mR/hr Ch. A2, B2 300 mR/hr 270 mR/hr SJAE Off Gas Log Rad Monitor Ch. A, B 35 mR/hr 25 mR/hr Rx Bldg Vent Ind/ Trip Unit Ch. A, B 0.6 mR/hr 0.6 mR/hr ,
y 1989 EVAIDATED EXERCISE Time = _1845 ! Message Number: 4 t= 00/45 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE L Messaae fort Control Room Simulated Plant Conditions: See attached Plant Data Messagt:
***THIS IS A DRILL *** ~<
,__.....ii, l
1989 EVAIDATED EXERCISE Time = __1845 MESSAGE NUMBER: 4 t= _00/45 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE FOR CONTROf T.F'R USE ONLY; Controller Information: o Data sheet reflects power reduction to 90% power at 100% rod line and reduced recirculation flow. Expected Actions:
1989 EVALUATED EEERCISE Time a .1845 Hassage Numbert 4 t= 00/45 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EEERCISE PLANT DATA PANEL 9-3 PANEL 9-5 STATUS PRESS (psig) ELQH(gpm) REACTOR POWER 90 % M RHR A STBY 50 0 REACTOR LEVEL 35 " NR RHR C STBY 50 REACTOR PRESSURE 980 (psig) RHR B SPC 240 6 7700 ELQH (10 lbs/hr) RHR D STBY 50 FEEDWATER A 3.6 CS A STBY 50 0 FEEDWATER B 3.6 CS B STBY 50 0 MAIN STEAM A 1.8 HPCI TRIPPED _ 50 0 MAIN STEAM B 1.8 Drywell Pressure Q221 (psig) MAIN STEAM C 1.8 Torus Level 1221 (feet) MAIN STEAM D 1.8 QEEE CLOSED CRD A FLOW 50 (gpm) MSIV B 0 CRD B FLOW 0 (gpm) SLC LEVEL 75 % PANEL 9-4 SLC PMP DISCH PRESS A 0 SLC PMP DISCH PRESS B 0 STATUS PRESS (psig) ELQH(gpm) RCIC AVAIL 50 0 RWCU A OPER 1180 160 MISCELLANEOUS PANELS RWCU B AVAIL 0 0 RRP A 83 % SPD DIESEL GEN 1 STBY RRP B 83 % SPD DIESEL GEN 2 STBY SBGT A STBY SBGT B OPER DRYWELL COOLING OPER TORUS WATER TEMP 80 9P DRYWELL TEMP 110 9P 1 1
l l 1989 EVAIDATED EXERCISE Time = 1845 Message: 4 COOPER NUCLEAR STATION t = _00/45 EMERGENCY PREPAREDNESS EXERCISE SPDS DATA teactor Power (Avg 1 APRM) teactor Level (in.)
+150 120
+100 N 100 50 80 0
60 50 40 100 20 150 0 30 15 0 +30 15 o Reactor Pressure (psig) 1200 1000 , 800 600 400 200 0 30 -15 o Drywell Pressure (psig) Drywell fenperature ('f) 300 75 250 60 200 45 150 30 100 15 50 0
*30 15 0 30 15 0 forus Level (in.) forus Water Temperature ('f)
*24 300 250
+12 200 0 150 100 12 50 !
24 0 30 15 0 30 15 0
_ _ _ .. -. = . . . - .. . .- . l COOPER NUCLEAR STATION RADIATION NONITORS 1989 EVALUATED REERCISE CLOCK TIME a 1845 [ SCENARIO TIME = 00/45
===========w....................===================================
STATION DESCRIPTION ! READING (mR/hr) i 1 Rx Bldg Fuel Pool Area (SE 5th Floor) 154 2 3 Rx Bldg Fuel Pool Area (SE 5th Floor) 1.5 Rx Bldg New Fuel Area (SE Sth Floor) 0.3 Rx Bldg Rx Water Cleanup Domineralizer 4 113 > 5 Area (SW 3rd Floor) ; Rx Bldg Sludge and Decant Pump Area 0.8 ; (S 2nd Floor) ; 6 Rx Bldg Neutron Monitor System Index 164 Area (TIP Room 1st Floor) 7 Rx Bldg Neutron Monitor System Drive 1.8 8 Mach Area (SE 1st Floor) Rx Bldg Control Rod Hydraulic Equipment 0.9 i t 9 Area (S ist. Floor) ' ! Rx Bldg Control Rod Hydraulic Equipment 9 i 10 Area (N 1st Floor) Rx Bldg HPCI Pump Room (SW Quad) 4 11 Rx Bldg RHR Pump Room (SW Quad) 5 12 Rx Bldg RHR Pump Room (NW Quad) L 24 13 Rx Bldg RCIC/CS Pump Room (NE Quad) 2 i 14 Rx Bldg CS Pump Room (SE Quad) 5 i 15 Turbine Bldg Turbine Front Standard 118 16 Turbine Bldg Mezz Control Corridor l 0.2 17 Turbine Bldg Basement Control Corridor .05 18 Turbine Bldg Rx Feed Pump Area 6 i 19 Turbine Bldg Condensate Pump Area .12 J 20 Control Room Main Control Room .02 l 21. Grade Level Control Corridor .19 22 Radwaste Control Room .03 23 Radwaste Pump Room 5 24 Radwaste Basement Equipment Area 4 25 Radwasta Domineralizer Valve Room 1.2 26 Radwaste Conveyor Aisle Operating Area 0.2 27 SPARE 28 Radwaste Lab Area .01 29 Centrifuge East 10 l 30 Centrifuge West 9 i L Panel 9-02 Personnel Airlock Area 903' 10 R/hr i Panel 9-02 Ladder 903' to 2nd Level 6 R/hr i OSH = Offscale High l
.1 ; _ . _ _ _ _ _ . . . _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
COOPER NUCLEAR STATION RADIATION MONITORS 1989 EVALUATED EEERCISE CLOCK TIME a 1845 SCENARIO TIME a 00/45
==================---===============.......-- .........................
- PANEL VBDQ Rx Bldg Vent Eff (RMV-RM-40) 1.0E-3 uCi/sec ERP Stack Normal Eff-(RMP-RM-3A) 5.5E-1 uCi/sec ERP Steck High Range (RMP-RM-3B) 0 uCi/see Turbine Bldg Vent Eff (RMV-RM-20A)- 1.5E-3 uCi/see Turbine Bldg High Range (RMV-RM -2 0 B) 0 uCi/sec RW/ARW Bldg Combined Eff (RMV-RM-30A) 1.5E-3 uCi/sec RW/ARW Bldg High Range (RMV-RM-30B) 0 uC i / s e c_ ..
PANEL 9-10 Main Steam Rad Monitor Ch. A1, B1 340 mR/hr 340 mR/hr Ch. A2, B2 290 mR/hr 270 mR/hr SJAE Off Gas Log Rad Monitor Ch. A, B 35 mR/hr 25 mR/hr Rx Bldg Vent Ind/ Trip Unit Ch. A, B 0.6 mR/hr 0.6 mR/hr l l-l 1 i f-e . .
3
- e. .
1989 EVALUATED EXERCISE Time = 1900_ Message Number: 5 t= 01/00 COOPER NUU RAR STATION EMERGENCY-PREPAREDNESS EYERCISE MESSAGE Mossaae for: Control Room i Simulated Plant Conditions: See attached Plant Data Megangg: l ***THIS IS A DRILL ***
1989 EVALUATED EXERCISE Time = 1900 MESSAGE NUMBER: 5 t= 01/00 SOOPER NUCLEAR STATION E!EBrdp*CY PREPAREDNESS EXERCISE MESSAGE i.. -FOR CONTROLLER USE ONLY:
' Controller Information:
Expected Actions:
,. ;g_.. _ . .
1989 EVALUATED EEERCISE Time a 1900 Message Numbert _)._ t= 01/00 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EEERCISE PLANT DATA PANEL 9-3 PANEL 9-5 STATUS PRESS (psig) FLOW (gpm) REACTOR POWER 90 % APRM RHR A STBY 50 0 REACTOR LEVEL 35 " NR RHR C STBY 50 REACTOR PRESSURE 980 (psig) s RHR B SPC 240 7700 FLOW (lo lbs/hr) RHR D STBY 50 FEEDWATER A 3.6
-CS A STBY 50 0 FEEDWATER B 3.6 CS B STBY 50 0 MAIN STEAM A 1.8 HPCI TRIPPED 50 0 MAIN STEAM B 1.8 Drywell Pressure 0,25 (psig) MAIN STEAM C 1.8 Torus Level 12.8 (feet) MAIN STEAM D 1.8 OPEN CLOSED CRD A FLOW 50 (gpm) ~MSIV 8 0 CRD B FLOW 0 (gpm)
SLC LEVEL 75 % PANEL 9-4 SLC PMP DISCH PRESS A 0 SLC PMP DISCH PRESS B 0 STATUS EBESS(psig) FLOW (gpm) RCIC AVAIL 50 0 RWCU A OPER _,1180 160 MISCELTANEOUS PANELS RWCU B AVAIL 0 0 RRP A 83 % SPD DIESEL GEN 1 STBY RRP B 83 % SPD DIESFL GEN 2 STBY SBGT A STBY SBGT B OPER DRYWELL COOLING OPER TORUS WATER TEMP 80 F DRYWELL TEMP 110 F 1
1989 EVALUATED EXERCISE Tjre e 1900 Message: 5 COOPER NUCLEAR STATION t= 01/00-EMERGENCY PREPAREDNESS EXERCISE SPDS DATA Reactor Power (Avg % APRM) Reactor Level (In.)
+150 120
+100 N 100
+50 60 0
60 50 40 100 20 150 0 30 15 0 30 15 0 Reactor Pressure (psig) 1200 1000 600 600 400 200 t 30 15 0 Drywell Pressure (psig) DryweLL Tenperature ('F) 300 75 250 60 200 45 150 30 100 15 50 0
' O 30 15 0 30 15 0 Torus Level (in.) Torm Water Temperature (OF )
+24 300 250
+12 200 0 150 100
-12 50 i
24 0 30 -15 0 -30 -15 0
l l COOPER NUCLEAR STATION RADIATION MONITORS 1989 EVALUATED EEERCISE CLOCK TIME a 1900 SCENARIO TIME = 01/00 STATION DESCRIPTION READING (mR/hr) 1 Rx Bldg Fuel Pool Area (SE Sth Floor) 154
- 2 Rx Bldg Fuel Pool Area (SE Sth Floor) 1.5
-3 Rx Bldg New Fuel Area (SE Sth Floor) 0.3 4 Rx Bldg Rx Water Cleanup Domineralizar 113 Area (SW 3rd Floor) 5 Rx Bldg Sludge and Decant Pump Area. 0.8 (S.2nd Floor) 6 Rx Bldg Neutron Monitor System Index 164 Area (TIP Room ist Floor) 7 Rx Bldg Neutron Monitor System Drive 1.8 Mach Area (SE ist Floor) 8 Rx Bldg Control Rod Hydraulic Equipment 0.9 Area (S ist Floor) 9 Rx Bldg Control Rod Hydraulic Equipment 9 Area (N ist Floor) 10 Rx Bldg HPCI Pump Room (SW Quad) 4 11 Rx Bldg RHR Pump Room (SW Quad) 5 12 Rx Bldg RHR Pump Room (NW Quad) 24 13 Rx Bldg RCIC/CS Pump Room (NE Quad) 2 14 Rx Bldg CS Pump Room-(SE Quad) 5 15 Turbine Bldg Turbine Front Standard 118 16 Turbine Bldg Mezz Control Corridor 0.2 17 Turbine Bldg Basement Control Corridor .05 18 Turbine Bldg Rx Feed Pump Area 6
-19 Turbine Bldg Condensate Pump Area .12 20 Control Room Main Control Room .02 21 Grade Level Control Corridor .19 22- Radwaste Control Room .03 23 Radwaste Pump Room 5 24 Radwaste Basement Equipment Area 4
'25 Radwaste Domineralizar Valve Room 1.2 26 Radwaste Conveyor Aisle Operating Area 0.2 27 SPARE 28 Radwaste Lab Area __
.01 29 Centrifuge East 10 30 Centrifuge West 9 Panel 9-02 Personnel Airlock Area 903' 10 R/hr Panel 9-02 Ladder 903' to 2nd Level 6 R/hr OSH = Offscale High i
COOPER NUCLEAR STATION RADIATION MONITORS 1989 EVALUATED EXERCISE CLOCK TIME a 1900 SCENARIO TIME = 01/00 PANEL VBDG Rx Bldg Vent Eff (RMV-RM-40)- 1.0E-3 uCi/sec ERP Stack Normal Eff (RMP-RM-3A) 5.SE-1 uCi/sec ERP Stack High Range (RMP-RM-3B) 0 uCi/sec Turbine Bldg Vent Eff (RMV-KM *OA) _.Ljlig-1 uCi/see Turbins' Bldg High Rarge (DW- Rf*-2C,B;. O _ qqifsec RW/ARW Bldg Combs nc:d '7f (10fY-K4-30? , 1.5E 3 g,C,tfuec RW/ARW bldu High Y Mgr A '-Pb 30B)
~
0 uci/nec
/EL 9. c "Mair 9 teak Rad M .icor Cc. Ai, ,1 340 mR/bE 340_.mR/hr Ch. A2. B2 ._290 mR/hr 270 MR/hr SJA1. O a. :-as *, e RY. Monitor C... A. B J mR/hr .25 mR/hr Rx Bldg Jent Ini/L np Unit Ch. A, u 0.6 mR/hr 0.6 mR/hr 1
i- i-.ii.--ii.-i..i-.-.----ui-
1989 EVAll!ATED EXERCISE Time = 1915 Message Number: 6 t= 01/15 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE Messaae for: Control Room
. Simulated Plant Conditions: See attached Plant Data Message:
***THIS IS A DRILL ***
l
1989 EVALUATED EXERCISE Time = 1915_ MESSAGE NUMBER: 6 t= 01/15 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS ENERCISE MESSAGE FOR CONTRQLI.ER USE ONLY
-Controller Informations o See Supplemental Scenarios No. 2,3, and 4 which start at about 1930.
Expected Actions
1989 EVALUATED EEERCISE 'fi n e = 1915 Message Numbers 5 t= 01/15 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE PLANT DATA PANEL 9-3 PANEL 9-5 STATUE PRESS (psig) ELQW(gpm) REACTOR POWER 90 % JWBM RHR A STBY 50 0 REACTOR LEVEL 35 " _ER_ RHR C STBY 50 REACTOR PRESSURE 980 (psig) 6 RHR B SPC 240 '700 ELQH (10 lbs/hr) RHR D STBY 50' FEEDWATER A 3.6 CS A STBY 50 0 FEEDWATER B 3.6 CS B STBY SO 0 MAIN STEAM A 1.8 HPCI TRIPPED 50 0 MAIN STEAM B 1.8 Drywell Pressure M (psig) MAIN STEAM-C 1.8 Torus' Level M (feet) MAIN STEAM D 1.B QEEE CLOSED CRD A FLOW 50 (gpm) MSIV 8 0 CRD B FLOW 0 (gpm) SLC LEVEL 75 % PANEL 9-4 SLC PMP DISCH PRESS A 0 SLC PMP DISCH PRESS B 0 STATUS PRESS (psig) ELQH(gpm) RCIC AVAIL 50 0 RWCU A OPER 1180 160 MISCELLANEOUS PANELS RWCU B AVAIL 0 0 RRP A 83 % SPD DIESEL GEN 1 STBY RRP B 83 % SPD DIESEL GEN 2 STBY SBGT A STBY SBGT B UPER DRYWELL COOLING OPER TORUS WATER TEMP 80 F DRYWELL TEMP 110 F
I 1989 EVALUATED EXERCISE , Time = 1915 Message: 6 COOPER NUCLEAR STATION t= 01/15 EMERGENCY PREPAREDNESS EXERCISE SPDS DATA Reactor Power (Avg % APRM) Reactor Level (in.)
+150 120
+100 100
- - - - - +50 80 0
60 50 40 100 20 150 0 30 15 0 30 15 0 Reactor Pressure (psig) 1200 1000 800
$ 600 400 200 0
-30 15 0 Drywell Pressure (psig). Drywell Tenp erature (OF )
300 75 250 60 200 45 150 30 100 15 50 0 0
-30 -15 0 -30 15 0 Tocus Level (in.) Torus Water Tenperature ('F)
+24 300 250
+n 200 0 150 100
-12 50 24 0 30 -15 0 -30 -15 0
COOPER NUCLEAR STATION _ RADIATION MONITORS
-1989 EVALUATED EXERCISE CLOCK TIME z 1915 SCENARIO TIME = 01/15
' STATION DESCRIPTION READING (mR/hr) 1 Rx Bldg Fuel Pool Area (SE Sth Floor) 154 2 'Rx Bldg Fuel Pool Area (SE Sth Floor) 1.5
'3 Rx B1cig New Fuel Area (SE Sth Floor) 0.3 4 Rx Bldg Rx Water Cleanup Demineralizer 113 Area (SW 3rd Floor) 5 Ibc Bldg Sludge and Decant Pump Area 0.8 (S 2nd Floor) 6 Rx Bldg Neutron Monitor System Index 164 Area-(TIP Room ist Floor)
? Rx Bldg Neutron Monitor System Drive 1.8 Mech Area (SE 1st Floor) 8 Rx Bldg Control Rod Hydraulic Equipment 0.9 Area (S ist Floor) 9 Rx Bldg Control Rod Hydraulic Equipment 9 i Area (N ist Floor) 10 Rx Bldg HPCI Pump Room (SW Quad) 3 11 Rx Bldg RHR Pump Room (SW Quad) _ 5 -_
12 Rx Bldg RHR Pump Room (NW Quad) '24 ___ 13 Rx Bldg RCIC/CS' Pump Room (NE Quad) 2 14_ Rx Bldg CS Punip Room (SE Quad) _ 5
- 15 Turbine Bldg Turbine Front Standard . 118 16 . Turbine Bldg Mezz Control Corridor- _AAJ
-17 Turbine Bldg Basement Control Corridor .05 ,
'18 Turbine Bldg Rx Feed Pump Area __ 6 19 Turbine Bldg Condensate Pump Area ,_12 20 Control Room Main Control Reem __,_.. 0:
21 Grade Level Control Corridor _ ..,_ ,,1; - 22 Radwaste Control Room 2 0; 23 Radwaste Pump Room ____5 24 Radwaste Basement Equipment Area 4 25 Radwaste Demineralizer Valve Room 1.2 26 Radwaste Conveyor Aisle Operating Area 0.2 27 SPARE 28 Radwaste Lab Area .01 29 Centrifuge East 10 30 Centrifuge West 9 Panel 9-02 Personnel Airlock Area 903' 10 R/hr Panel 9-02 Ladder 903' to 2nd Level 6 R/hr OSH = Offscale High
COOPER NUCLEAR STATION RADIATION MONITOR 8 1989 EVALUATED EXERCISE CLOCK TIME a 1915 8CENARIO TIME a 01/15
======:---....--==.............---============.----...--.--.......u===
PANEL VBDG Rx Bldg Vent Eff (RMV-RM-40) 1.0E-3 uCi/sec ERP Stack Normal.Eff (RMP-RM-3A) 5.SE-1 uCi/sec ERP Stack High Range (RMP-RM-3 B) 0 u C i / s e c _ ._ _ Turbine Bldg Vent Eff (RMV-RM-20A) _1.SE-3 uCi/sec Turbine Bldg High Range (RMV-RM-20B) o uci/see RW/ARW' Bldg Combined Eff (RMV-RM-30A) 1.5E-3 uCi/sec RW/ARW Bldg High Range (RMV-RM-30B) 0 uCi/sec _ _4, PANEL 9-10 Main Steam Rad Monitor Ch. A1, B1 340 mR/hr 340 mR/hr Ch. A2, B2 290 mR/hr 270 mR/hr SJAE Off Gas Log Rad Monitor Ch. A, B 35 mR/hr 25 mR/hr Rx Bldg Vent Ind/ Trip Unit Ch. A, B 0.6 mR/hr 0.6 mR/hr ..--_._--_L___ ~___'_.__'_ -_ - - - _ -- - _ _ _ - - - -- - - - ~ . , - 4 n
l 1989 EVALUATED EXERCISE Time = 1930 Message-Number: 7 t= 01/30 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MES8h0E Message for Control Room Simulate! Plant conditions: See attached Plant Data Message:
*** TRIS IS A DRILL ***
Annunciators in the Control Room include: RECIRC LOOP A OUT OF SERVICE PNL 9-4-1/1-3 RECIRC LOOP B OUT OF SERVICE 'NL 9-4-1/2-3 LPRM UPSCALE ' 'NL 9 1/9-6 LPRM DOWNSCALE PNL 9-5-1/9-5 APRM UPSCALE (rod block) PNL 9-5-1/8-6 AME DOWNSCALE _ PNL 9-5-1/8-5 MAIN STEAM LINE HI RADIATION PNL 9-4-2/3-1 Indications in the Control Room Includo: Various LPRM UPSCALE and LPRM DOWNSCALE white and amber lights blinking on full core display. Various LPRM UPSCALE and LPRM DOWNSCALE lights sealed in on 9-14. Core Flow is 25 Mlb/hr. Reactor Recirc Pumps A/B MG sets field breakers GREEN lights on. Other RRP A/B MG set indications are as follows: Drive motor amps drop off. Generator amps / volts drop to zero. All othr2r breaker indictitions are normal. i
1989 EVALUATED EXERCISE Time = 1930
- Message Numbert 7 t= 01/30 QQOPER NUCLEAR STATION M .8.E_.I EE.GIAA ME.EAGI L
k FOR CONTROLLIER USE ONLY
- controller Information
~
I A loose jumper cable left by an I&C technician investigating the cause of the failure of the RPT indicating lights, inadvertantly - shorts terminals in Panel 9-42, causing a trip of both of the
. recirc pump generator field breakers. This causes an ime.ediate '
loss of the recirc pumps with no coastdown. Undamped reactor power oscillations begin immediately. It is postulated that this unanalyzed reactor power transient damages approximately 5% of the fuel cladding. This fuel damage mechanism was described in NRC - Dulletin 88--07. Expected Actions: Control Room operators observe the power oscillations and take
- actions to control the reactor. Main Steam high radiation alarms I
provide first indication of fuel damage. Concurrently with operator action-to manually scram the reactor, the Main Steam High-High Radiation alarm causes a Group 1 (Main Steam) isolation and reactor scram. DELIVER MESSAGE 7.1X AS OPERATOR 8 TAKE ACTION TO MANUALLY SCRAM THE REACTOR. l se
~4' , . .
r dONTROLLER. tasc odty- "
",^*'"EUL c:R ATIO N FLOW NS] ABILITY 100 -
yTa
'p, TYPICAL PUMP CONSTANT SPEED l ggE LIN E sea *
- a 80 d
OUN
$ TYPICAL FLOW #
2 A N CONTROL LINES C FLOW CONTROL LINE '. ex- : O* \ y
.o w::
LINE
/ \ -
j
/ ,
20 f LOW FW RECIRC. RUN8ACll LINE MINIMUM I ggW 956O U (2 PUMPS) SC.$ g , a - -
- 20. 30 '40 60 60 70 80 90 100 110 120 CORE FLOW, % of 73.5 Mlb/hr
- POWER __
TO FLOW MAP . _ - - . - - c, m.,, .
1989 EVALUATED EXERCISE Time = 1930 Wessage Number 7 t= 01/30 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCI8L' PLANT DATA PANEL 9-3 PANEL 9-5 STATUS PRESS (psig) ELQH(gpm) REACTOR POWER _ 44 % AEBM RHR A STBY 50 0 REACTOR LEVEL 40 " NR RHR C STBY 50 REACTOR PRESSURE 945 (psig) s RHR B SPC 240 7700 ELQH (lo lbs/hr) RHR D STBY 50 FEEDWhTER A 2.1 CS A STBY 50 0 FEEDWATER B 2.1 CS B STBY 50 0 MAIN STEAM A 1.05 HPCI TRIPPED 50 0 MAIN STEAM B 1.05 Drywell Pressure 2215 (psig) MAIN STEAM C 1.05 Torus Level M (feet) MAIN STEAM D _,1221 QEIH CLOSED CRD A FLOW 50 (gpm) MSIV 8 0 CRD B FLOW' O (gpm) SLC LEVEL 75 % EAHEL 9-4 SLC PMP DISCH PRESS A 0 SLC PMP DISCH PRESS B __ _0 ST?.TUS PRESS (psig) ELQS(gpm) RCIC AVAIL 50 0 RWCU A OPER 1180 160 MISCELIANEOUS PANELS RWCU B AVAIL 0 0 RRP A 0 % SPD DIESEL GEN 1 STBY BRP B 0 % SPD DIESEL GEN 2 STBY SBGT A STBY SBGT B OPER DRYWELL COOLING OPER TORUS WATER TEMP 80 9P DRYWELL TEMP 110 IF
Y ey p , t 1989-EVALUATED EXERCISE Timo = 1930 Message: 7 COOPER NUCLEAR STATION t= 01/30 EMERGENCY PREPAREDNESS EXERCISE SPDS DATA Reactor Power (Avg % APRM) Reactor Level (in.)
+150 120
+100 100 80 0
60 ld' 50 40 100 20 150 0 30 15 0 30 -15 0 Reactor Pressure (psig) 1200 1000 bat 800 600 400 200 0 30 15 0 Drywell Pressure (psig) Drywell Temperature (OF ) 300 75 250 60 200 45 150 30 100 15 50 0 0 30 15 0 30 -15 0 i' t f orus Level (in.) Torus Water Tenperature (CF)
+24 300 250
+12 200 0 150 100 12 50 24 0 30 -15 0 -30 -15 0 1
- ~ < , ,
k ? i COOPER NUCLEAR STATION RADIATION MONITOR 8
. i '
1989 EVALUATED EXERCISE CLOCK TIME a 1930 SCENARIO TIME = 01/30 l STATION DESCRIPTION READING (mR/hri j 1 Rx Bldg Fuel Pool Area (SE Sth Floor) 154 2 Rx Bldg Fuel Pool Area (SE Sth Floor) 1.5 3 Rx Bldg New Fuel Area (SE Sth Floor) 0.3 4 Rx Bldg Rx Water Cleanup Demineralizer 113 Area (SW.3rd Floor) 5 Rx Bldg Sludge and Decant Pump Area 0.8 (S 2nd Floor) 6 Rx Bldg Neutron Monitor System Index 164 Area (TIP Room ist Floor)- 7 Rx Dldg Neutron Monitor System Drive 1.8 - Mech Area-(SE 1st Floor) 8 Rx Bldg Control Rod Hydraulic Equipment , 0.9 Area (S ist Floor) 9 Rx Bldg Control Rod Hydraulic Equipment 9 Area (N-1st Floor) 10 Rx Bldg HPCI Pump Room (SW Quad) 0.3 11 Rx Bldg RHR Pump Room (SW Quad) 5 12 Rx Bldg RHR Pump Room (NW Quad) 24 13 Rx Bldg RCIC/CS Pump Room (NE Quad) 2 14 Rx Bldg CS Pump Room (SE Quad) 5
- 15. Turbine Bldg Turbine Front Standard 58 16 Turbine Bldg Mezz Control Corridor 'O.2 17- Turbine Bldg Basement Control Corridor .05 18 Turbine Bldg Rx Feed Pump Area 6 19 Turbine Bldg Condensate Pump Area .
.12 20- Control Room Main Control Room .02 21 Grade Level' Control Corridor .19 3, 22 Radwaste Control Room .03 23 Radwaste Pump Room 5 24 Radwaste Basement Equipment Area 4 25 Radwaste Demineralizer Valve Room 1.2 26' Radwaste Conveyor Aisle Operating Area 0.2 27 SPARE
- 28- Radwaste Lab Area .01 29 Centrifuge East 10 30 Centrifuge West 9 Panel 9-02 Personnel Airlock Area 903' 7 R/hr Panel 9-02 Ladder 903' to 2nd Level 4 R/hr OSE'= Offscale High
.m
_. .- - - . ~ _ . . . _
+
COOPER NUCLEAR STATION RADIATION MONITOR 8 1989 EVALUATED EXERCISE CLOCK TIME z' 1930 SCENARIO TIME a 01/30 ,
.............. w.......................................................
PANEL VBDG Rx Bldg Vent Eff (RMV-RM-40) 1.0E-3 uCi/sec ERP Stack Normal Eff (RMP-RM-3A) 5.5E-1 uCi/sec ERP Stack High Range (RMP-RM-3B) 0 uCi/see Turbine Bldg Vent Eff (RMV-RM-20A) 1.5E-3 uCi/sec Turbine Bldg High Range (RMV-RM-20B) 0 uCi/sec RW/ARW Bldg Combined Eff (RMV-RM-30A) 1.5E-3 uCi/sec RW/ARW Bldg High Range (RMV-RM-30B) 0 uCi/sec PANEL 9-10 Main Steam Rad Monitor Ch. A1, B1 160 mR/hr 160 mR/hr Ch. A2, B2 160 mR/hr 160 mR/hr SJAE Off Gas Log Rad Monitor Ch. A, B 35 mR/hr 25 mR/hr Rx Bldg Vent Ind/ Trip Unit Ch. A, B 0.6 mR/hr 0.6 mR/hr l l. l l. l l 1
l 1989 EVALUATED EXERCISE Time = ~1933 , Message Number 7.1X t = ~01/33 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE ! Message fort control Room Simulated Plant Conditions: See attached Plant Data Messages
***THIS IS A DRILL ***
Annunciators in the control Room include: MANUAL SCRAM TRIP SYSTEM A/B PNL 9-5-?/4,5-2 MAIN STEAM LINE HI RAD TRIP PNL 9-5-2/3-3
- XAIN STEAM ISOLATION VLV NOT FULL OPEN TRIP PNL 9-5-2/1-2 l REACTOR VESSEL HIGH PRESSURE TRIP PNL 9-5-2/2-1 REACTOR LOW WATER #2 PNL 9-3-1/8-2 AUTOSCRAM-TRIP SYSTEM A/B PNL 9-5-2/8,9-1
( AUTO BLOWDOWN CONTROL POWER FAILURE PNL 9-3-4/1-1 L LOW LOW SET A OR B POWER LOST PNL 9-3-4/1-3 l SAFETY OR RELIEF VALVE LEAKING PNL 9-3-4/2-1 RELIEF VALVE OPEN PNL 9-3-4/3-1 Indications in the Control Room include: All control rods fully inserted. Level.has stabilized and is increasing. Red and green position lights extinguished immediately for all SRVs. Amber lights for the five 1080 and 1090 set SRVs illuminate initially, then reactor pressure cycles between 1080 and 960 lbs. l coincident with amber lights for the two 1080 set SRVs. Group 1,2,3,6 isolations are successful except: AOG steam supply inboard isolation valve MO-920, red light lit, green light stays off, AOG steam supply outboard isolation valve MO-921, red and l green lights lit for 3 seconds, then both out. 1
,e a .a a.- a n--- <..a - -
4 i
~
1989 EVALUATED EXERCISE Time = *1933 MESSAGE NUMBER: 7.1X t= '01/33 l l COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE l FOR CONTROLLER USE ONLY: Controller Information: L o. The operators manually scram the reactor concurrent with an automatic scram caused by 3 X Normal Main Steam Line Radiation. All control rods fully insert and the reactor is l shutdown. l _o The vessel level transient causes the appropriate containment isolations, and RCIC starts on -37_" reactor water level, o See Supplemental Scenario Number 3. SRVs open (mechanically)- in response to the pressure transient. However, the j electrical function of the SRVs is lost (see SS #3). o The containment isolation in response to this event is l successful with the exception of AOG Steam Supply Isolation l Valves MO-920 and MO-921. This establishes the release path ! out of AOG to the Elevated Release Point. This is an elevated, monitored, and filtered release.
- Expected Actions o Enter Annunciator Response Procedures and EOPs. Verify that expected. actions in response to the transient have occurred.
o Investigate equipment failures. l o Emergency Director declare a SITE AREA EMERGENCY in accordance
-with EPIP 5.7.1, Attachment B, page 7 of 23, Initiating Condition 1.3.2, " Radiological gaseous effluent releases resulting in THYROID dose rate at the site boundary of.125 Mrem as determined by ADAM, DOSE, hand calculations, or in-field surveys, o Emergency Director implement EPIP 5.7.4, " SITE AREA l EMERGENCY".
o Emergency Director implement EPIP 5.7. 6, " Notification", EPIP 1 5.7.9, " Activation of EOF", EPIP 5.7.11, "Evaauation of Non-Essential Personnel", EPIP 5.7.16, " Release Rate Determination", EPIP 5.7.17, " Dose Assessment", and EPIP 5.7.18/19, "On-Site, Off-site and Site Boundary Monitoring". l t 1
1989 EVALUATED EXERCISE Time = ~1933 Message Number: 7.1X t = ~01/33 t COOPER EUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE PLANT DATA PANEL 9-3 PANEL 9-5 STATUS PRESS (psig) FLOW (gpm) REACTOR POWER 0% APRM RMR A ST3Y 50 0 REACTOR LEVEL -45 " _HE_ RHR C STBY 50 REACTOR PRESSURE 1090 (psig) RHR.B' SPC _ 240 7700 FLOW 8 (10 lbs/hr) RHR D STBY 50 FEEDWATER A 0.0 CS A STBY 50 0 FEEDWATER B 0.0 CS B- STBY 50 0 MAIN STEAM A 0.0 HPCI TRIPPED 50 0 MAIN STEAM B 0.0 t Drywell Pressure 0,25 (psig) MAIN STEAM C 0.0 Torus Level 12.8 (feet) MAIN STEAM D 0.0 QEEH CLOSED CRD A FLOW 90 (gpm) MSIV O 8 CRD B FLOW 0 (gpm)
~ l i \
l SLC LEVEL 75 % 1 PANEL 9-4 SLC PMP DISCH PRESS A 0 SLC PMP DISCH PRESS B 0 l ETATUS PRESS (psig) FLOW (gpm) _ L RCIC OPER 1290 416 I RWCU A ISOL 0 0 MISCELLANEOUS PANELS RWCU B ISOL 0 0 RRP A 0 % SPD DIESEL GEN 1 STBY l RRP B 0 % SPD DIESEL GEN 2 STBY l SBGT A OPER SBGT B OPER DRYWELL COOLING ISOL l TORUS WATER TEMP 80 Y DRYWELL TEMP 110 Y , l 1
._ s--- ., 4
;- - v: ?
e i 1989 EVALUATED EXERCISE Time = ~1933 Message: 7.1X COOPER NUCLEAR STATION t = ~01 (3J EMERGENCY PREPAREDNESS EXERCISE SPDS DATA Reactor Power ( Avg % APRM) Reactor Level (in.)
+150
, 120
+100 100 80 N 0 i 60 ll 50 100 20
-150 0
30 15 0 30 15 0 Reactor Pressure (psig) 1200 1000 800 6 600 400 200 0 30 15 0 Drywell Pressure (psig) DryweLL Tenperature (OF ) 300 -I 75 250 60 200 45 . 150 E 30 100 15 50 0 0 30 15 0 30 -15 0 Torus Level (in.) Torus Water temperature (OF )
+24 300 250
+12 200 0 150 100 12 50 24 0
-30 -15 0 -30 -15 0
# 4# 4* E kt% IMAGE EVALUATION ///jg/j 'I%g,#,
g f/ TEST TARGET (MT-3) Y 40 4 gqr>fy&W
%f[f 1.0 if La M 5 [N M ll E5: HIM m
---=
I.25 1.4 1.6 l.- 4 150mm > 4 6" > [*%//>//
, y,,,
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.>,4y>ff a 4p
;a=w
+h .
kNNO O +8>@'# k- IMAGE EVALUATION dd
////psg[*"+p#,
gpxy v @ TEST TARGET (MT-3) 4 sW '",,
/,
l.0 Em M m m g'"n b tu l,l fM bb D8 1.25 1.4 1.6 4 150mm
- 4 6" >
*' /f4%
[y 23j,p % , __ _
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/
O i f4 ff
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't IMAGE EVALUATION 8
//o//%[>[ \'% ff' TEST TARGET (MT-3) ///[ %[ ' p &f/g
} \\
//777 1.0 l tam
;[j I!!!E i,l [t: He l.8 j
1.25 1.4 i.6 4 150mm > 4 6" >
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4 V +$9 $ IMAGE EV ALUATION YkkM@' 1[.
/ TEST TARGET (MT-3) f[f[+g,
///gfNY /*,
4 k//f7 l.0 E L'a BLA
'f (( Eld l,1
[f EM M1 l.25 1.4 1.6 4 150mm > 4 6" >
# %y ,,
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p COOPER NUCLEAR STATION L , RADIATION MONITORS 1989 EVALUATED EXERCISE CLOCK TIME a 1933 SCENARIO TIME = 01/33 STATION DESCRIPTION READING (mR/hr) 1 Rx-Bldg Fuel Pool Area (SE Sth Floor) 154 2 Rx Bldg Fuel Pool Area (SE 5th Floor) 1.5 3~ Rx Bldg New Fuel Area (SE 5th Floor) 0.3 4 Rx Bldg Rx Water Cleanup Demineralizer 113 Area (SW.3rd Floor) 5 Rx Bldg Sludge and Decant Pump Area 0.8 (S 2nd Floor) 6 Rx Bldg Neutron Monitor System Index 164 Area-(TIP Room ist Floor) 7 Rx Bldg Neutron Monitor System Drive 20 Mech Area (SE 1st Floor) 8 Rx Bldg Control Rod Hydraulic Equipment 18 Area (S ist Floor) 9 Rx Bldg Control Rod Hydraulic Equipment 18 Area (N ist Floor) 10 Rx Bldg HPCI Pump Room (SW Quad) 3 11 Rx Bldg RHR Pump Room (SW Quad) 35 12 Rx Bldg RER Pump Room (NW Quad) 35 13 Rx Bldg RCIC/CS Pump Room (NE Quad) 35 14 Rx Bldg CS Pump Room (SE Quad) 35 15 Turbine Bldg Turbine Front Standard 20 16 Turbine Bldg Mezz Control Corridor 0.2 17 Turbine Bldg Basement Control Corridor .05 18 Turbine Bldg Rx Feed Pump Area 6 19 Turbine Bldg Condensate Pump Area .12 20 Control Room Main Control Room .02 21 Grade Level Control Corridor .19 22 Radwaste Control Room .03 23 Radwaste Pump Room 5 24 Radwaste Basement Equipment Area 4 25 Radwaste Demineralizer Valve Room 1.2 26 Radwaste Conveyor Aisle Operating Area 0.2 27 SPARE 28 Radwaste Lab Area .01 29 Centrifuge East 10 30 Centrifuge West 9 Panel 9-02 Personnel Airlock Area 903' 225 R/hr Panel 9-02 Ladder-903' to 2nd Level 225 R/hr OSH = Offscale High
COOPER NUCLEAR STATION RADIATION NONITORS 1989 EVALUATED EXERCISE CLOCK TIME z 1933 8CENARIO TIME a 01/33
===========================================================
PANEL VBDG Rx Bldg Vent Eff (RMV-RM-40) 1.0E-3 uCi/sec ERP Stack Normal Eff (RMP-RM-3A) 5.5E-1 UCi/sec ERP Stack High Range (RMP-RM-3B) 0 uCi/see Turbine Bldg Vent Eff (RMV-RM-20A) 1.5E-3 uCi/sec Turbine Bldg High Range (RMV-RM-20B) 0 uCi/see RW/ARW Bldg Combined Eff (RMV-RM-30A) 1.0E-3 uCi/sec RW/ARW Bldg High Range (RMV-RM-30B) 0 uci/see PANEL 9-10 Main Steam Rad Monitor Ch. A1, B1 2000 mR/hr 2000 mR/hr Ch. A2, B2 2000 mR/hr 2000 mR/hr SJAE Off Gas Log Rad Monitor Ch. A, B 35 mR/hr 25 mR/hr Rx Bldg Vent Ind/ Trip Unit Ch. A, B 0.6 mR/hr 0.6 mR/hr
t i 1989 EVALUATED EXERCISE Time = 1945 Message Number: 8 t= 01/45 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE Messace fort Control Room ' Simulated Plant Conditions: See attached Plant Data Messages
***THIS IS A DRILL ***
Annunciators received in the Control Room include: RCIC Turbine Tripped PNL 9-4-1/8-1 Indications in the Control Room include: RCIC turbine trip throttle valve and min. t' low valves are closed. The trip is apparently due to overspeed, since the trip can not be reset from the Control Room l l 1 l l I
1989 EVALUATED EXERCISE Time a 1945 MESSAGE NUMBER: _J_ t= 01/45 , COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE FOR CONTROLLER USE ONLY: Controller Informations o RCIC has. tripped due to a spurious overspeed trip signal. The RCIC overspeed trip mechanism has come apart and requires reassembly. RCIC is inoperable for the remainder of the scenario. See SS#5. j o Operators may reset isolations, and restore DW cooling, RWCU, etc., and secure SBGT. Adjust data sheets as necessary, o SBGT is assumed to operate throughout the scenario, if operators attempt to secure SBGT, give credit for this action , and explain that for the scenario data package, it is assumed ' to remain in service throughout. ! i o Adjust RWL downward if operators do not take actions to maximize CRD flow. Expected Actionst o Maximize CRD flow. l l
i l 1989 EVALUATED EXERCISE Time = 1945 1 f Messago Number: 8 t= 01/45 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE PLANT DATA I PANEL 9-3 PANEL 9-5 STATUS PRESS (psig) FLOW (gpm) REACTOR POWER 0% APRM RHR A STBY 50 0 REACTOR LEVEL 31 " _HB_
'RHR C STBY 50 REACTOR PRESSURE 1080 (psig)
IU'R B EEg_ 240 6 7700 FLOW (10 lbs/hr) RHR D STBY= 50 FEEDWATER A 0.0 CS A STBY 50 0 FEEDWATER B 0.0 CS B STBY 50 0 MAIN STEAM A 0.0 HPCI TRIPPED __ 50 0 MAIN STEAM B 0.0 Drywell Pressure 0.25 (psig) MAIN STEAM C 0.0 Torus Level 12.8 (feet) MAIN STEAM D 0.0 OPEN CLOSED CRD A FLOW 50 (gpm) MSIV O 8 CRD B FLOW 0 (gpm) SLC LEVEL 75 % PANEL 9-4 SLC PMP DISCH PRESS A 0 SLC PMP DISCH PRESS B 0 STATUS . PRESS (psig) FLOW (gpm) RCIC TRIPPED 50 0 RWCU A ISOL 0 0 MISCELLANEOUS PANELS l- RWCU B ISOL 0 0 RRP A 0 % SPD DIESEL GEN 1 STBY
.IUU) B 0 % SPD DIESEL GEN 2 STBY SBGT A OPER SBGT B OPER DRYWELL COOLING ISOL TORUS WATER TEMP 81 F DRYWELL TEMP 112 F i
~ . - _ _ -_
5 1989. EVALUATED EXERCISE Time = 1945
- Message: 8- COOPER NUCLEAR STATION t= 01/45
-EMERGENCY PREPAREDNESS EXERCISE SPDS DATA Reactor Power ( Avg % APRM) Reactor Level (in.)
+150 120
*100 100
__ . +50 80 _ 0 60 50 40 100 20 150 o 30
- l5 t1 0 30 12 0 Reactor Pressure (psig) 1200
^/V ,-
800 , 600 400 200 0
+30 11 0 Orywell Pressure (psig) Drywell Testwroture (DF )
300 75 250 60 200 45 150 30 100 15 50 0 0 15 0 30 -15 0 Torus level (in.) Torus Water Tenperature (OF )
+24 300 250
+12 200 0 150 100 12 50
-24 0
-30 15 0 -30 15 0
COOPER NUCLEAR STATION RADIATION MONITORS 1989 EVALUATED EXERCISE CLOCK TIME a 1945 SCENARIO TIME = 01/45
===================================================================
STATION DESCRIPTION READING (mR/hr) 1 Rx Bldg Fuel Pool Area (SE Sth Floor) 154 2- Rx Bldg Fuel Pool Area (SE 5th Floor) 1.5 3 Rx Bldg New Fuel Area (SE Sth Floor) 0.3 4 Rx Bldg Rx Water Cleanup Demineralizer 113 Area (SW 3rd Floor) 5 Rx Bldg Sludge and Decant Pump Area 0.8 (S 2nd Floor) 6 Rx Bldg Neutron Monitor System Index 164 Area (TIP Room ist Floor) 7 Rx Bldg Neutron Monitor System Drive 25 Mech Area (SE 1st Floor) 8 Rx Bldg Control Rod Hydraulic Equipment 20 Area (S 1st Floor) 9 Rx Bldg Control Rod Hydraulic Equipment 20 Area (N ist Floor) 10 Rx Bldg HPCI Pump Room (SW Quad) 4 11 Rx Bldg RHR Pump Room (SW Quad) 40
- - 12 RX Bldg RHR Pump Room (NW Quad) 40 l 13 Rx Bldg RCIC/CS Pump Room (NE Quad) ,
40 l 14- Rx Bldg CS Pump Room (SE Quad) 40 l 15- Turbine Bldg Turbine Front Standard 20 1 16 Turbine Bldg Mezz Control Corridor 0.2 L 17 Turbine Bldg Basement Control Corridor .05 L 18 Turbine Bldg Rx Feed Pump Area 6 1 19 Turbine Bldg Condensate Pump Area .12 L 20 Control Room Main Control Room .02 l 21 Grade Level Control Corridor .19 L 22 Radwaste Control Room .03 l 23 Radwaste Pump Room 5 24 Radwaste Basement Equipment Area 4 25 Radwaste Demineralizer Valve Room 1.2 26 Radwaste Conveyor Aisle Operating Area 0.2 27' SPARE 28 Radwaste Lab Area .01 29 Centrifuge East 10 o 30 Centrifuge West 9 l Panel 9-02 Personnel Airlock Area 903' 250 R/hr Panel 9-02 Ladder 903' to 2nd Level 250 R/hr OSH = Offscale High l l
i COOPER NUCLEAR STATION RADIATION MONITORS 1989 EVALUATED EXERCISE CLOCK TIME a 1945 SCENARIO TIME a 01/45
=======================================================================
EANEL VBDG Rx Bldg Vent Eff (RMV-RM-40) 1.0E-3 uCi/see ERP Stack Normal Eff (RMP-RM-3A) 4.3E+4 uCi/sec ERP Stack High Range (RMP-RM-3B) o uci/sec Turbine Bldg Vent Eff (RMV-RM-20A) 1.5E-3 uCi/sec Turbine Bldg High Range (RMV-RM-20B) 0 uCi/see ' RW/ARW Bldg Combined Eff (RMV-RM-30A) 1.0E-3 uCi/sec RW/ARW Bldg High Range (RMV-RM-30B) 0 uCi/see PANEL 9-10 Main Steam Rad Monitor Ch. A1, B1 1000 mR/hr 1000 mR/hr Ch. A2, B2 1000 mR/hr 1000 mR/hr SJAE Off Gas Log Rad Monitor Ch. A, B . 20 mR/hr 15 mR/hr Rx Bldg Vent Ind/ Trip Unit Ch. A, B 0.6 mR/hr 0.6 mR/hr
1989 EVALUATED EXERCISE Time = 2000 Message Number: 9 t= 02/00 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE Messaae for: Control Room Simulated Plant Conditions: See attached Plant Data Epssaae:
***THIS IS A DRILL ***
l l I 4
1989 EVAIDATED EXERCISE Time = 2000 MESSAGE NUMBER: 9 t= 02/00 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE FOR CONTROLLER USE ONLY: Controller Information: Expected Actions:
Y, 1999 EVALUATED EXERCISE Time = 2000 Message Number: 9 t= 02/00 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE PLANT DATA 1 PANEL 9-3 PANEL 9-5 STATUS PPESS(psig) FLOW (gpm) REACTOR POWER 0% APRM RHR A STBY 50 0 REACTOR LEVEL 31 " NR RHR C STBY 50 REACTOR PRESSURE 1080 (psig) l 6 RHR B SPC 240 7700 ELQH (10 lbs/hr) RHR D STBY 50 FEEDWATER A 0.0 CS A STBY 50 0 FEEDWATER B 0.0 CS.B STBY 50 0 MAIN STEAM A 0.0 HPCI TRIPPED 50 0 MAIN STEAM B 0.0 Drywell Pressure 0.25 (psig) MAIN STEAM C 0.0 Torus Level 12.8 (feet) MAIN STEAM D 0.0 OPEN CLOSED CRD A FLOW 90 (gpm) MSIV O 8 CRD B FLOW 90 (gpm) l SLC LEVEL 75 % PANEL 9-4 SLC PMP DISCH PRESS A 0 L SLC PMP DISCH PRESS B 0 STATUS PRESS (psig) FLOW (gpr) RCIC TRIPPED 50 0 l- RWCU A ISOL 0 0 MISCELLANEOUS PANELS RWCU B ISOL 0 0 RRP A 0 % SPD DIESEL GEN 1 STBY RRP B 0 % SPD DIESEL GEN 2 STBY , j SBGT A STBY l SBGT B OPER l' DRYWELL COOLING ISOL TORUS WATER TEMP 82 F DRYWELL TEMP 114 F l l
. _ _ _ _ ___ _ _ _ _ . . ~ . _ _ . _ _ . _ _ _ . . - _ _ _ _ _ _ . _ ___
k I 1989 EVALUATED EXERCISE Time a 1930 Message Number:- 7 t= 01/30 1 COOPER NUCLEAR STATION 1 EMERGENCY PREPAREDNES8 EXERCI8E MESSAGE Messace fort Control Room Simulated Plant Conditions: See attached Strip Chart Messace: ,
***THIS IS A DRILL ***
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1 1989. EVALUATED' EXERCISE Time = 2000 Message: 9 COOPER NUCLEAR STATION t= 02/00 l EMERGENCY PREPAREDNESS EXERCISE SPDS DATA Reactor Power (Avg 1 APRM) Reactor Level (In.)
+150 120
+100 100
+50 g . g yyy _ ._
0
. 60 50 h .joo 20 150 0 1 30 15 0 30 15 0 Reactor Pressure (psig) 1200 600 400 200 0
30 15 0 DryweLL Pressure (psig) Drywell Tenperature (OT ) 300 75 250 60 200 45 150 30 100 15 50 0 0 33 15 0 30 -15 0 f orus Level (in.) forus Water Tenperature (DF)
+24 300 250
+12 200 0 150 100
-12 50 24 0 30 15 0 - 30 -15 0
^
4 1 a L COOPER NUCLEAR STATION RADIATION MONITORS CLOCK TIME a 2000 1989 EVALUATED FIERCISE SCENARIO TIME = 02/00 STATION DESCRIPTION READING (mR/hr) 1 Rx Bldg Fuel Pool Area (SE Sth Floor) 154 2 Rx Bldg Fuel Pool Area (SE Sth Floor) 1.5 1 3 Rx Bldg New Fuel Area (SE Sth Floor) 0.3 4 Rx Bldg Rx Water Cleanup Demineralizer 113 , Area-(SW 3rd Floor) l 5 Rx Bldg Sludge and Decant Pump Area 0.8 j (S 2nd Floor) i 6 Rx Bldg Neutron Monitor System Index 164 Area (TIP Room ist Floor) 7 Rx Bldg Neutron Monitor System Drive 18 Mech Area (SE 1st Floor) 8 Rx Bldg Control Rod Hydraulic Equipment 13 Area (S ist Floor) 9 Rx Bldg Control Rod Hydraulic Equipment 13 j Area (N ist Floor) 10 Rx Bldg HPCI Pump Room (SW Quad) 6 l 11 Rx Bldg RHR Pump Room (SW Quad) 60 12 Rx Bldg RHR Pump Room- (NW Quad) 60 13 Rx Bldg RCIC/CS Pump Room (NE Quad) 60 14 Rx Bldg CS Pump Room (SE Quad) 60 15 Turbine Bldg Turbine Front Standard 2 16 Turbine Bldg Mezz Control Corridor 0.2 17 Turbine Bldg Basement-Control Corridor .05 18 Turbine Bldg Rx Feed Pump Area 6 19 Turbine Bldg Condensate Pump Area .12 20 Control Room Main Control Room .02 21 Grade Level Control Corridor .19 22 Radwaste Control Room .03 23 Radwaste Pump Room. 5 24 Radwaste Basement Equipment Area 4 25 Radwaste Demineralizer Valve Room 1.2 26 Radwaste Conveyor Aisle Operating Area 0.2 27 SPARE 28 Radwaste Lab Area .01 29 Centrifuge East 10 30 Centrifuge West 9 Panel 9-02 Personnel Airlock Area 903' 225 R/hr Panel 9-02 Ladder 903' to 2nd Level 225 R/hr OSH = Offscale High
COOPER NUCLEAR STATION RADIATION MONITORS 1989 EVALUATED EXERCISE CLOCK TIME a 2000 I 8CENARIC TIME a 02/00
=======================================================================
PANEL VBDG Rx Bldg Vent Eff (RMV-RM-40) 1.0E-3 uCi/sec ERP Stack Normal Eff (RMP-RM-3A) 4.1E+4 uCi/sec ERP Stack High Range (RMP-RM-3B) 0 uci/see Turbine Bldg Vent Eff (RMV-RM-20A) 1.5E-3 uCi/sse Turbine' Bldg High Range (RMV-RM-20B) 0 uCi/see RW/ARW Bldg Combined Eff (RMV-RM-30A) 1.0E-3 uCi/sec RW/ARW Bldg High Range (RMV-RM-308) o uCi/see l PANEL 9-10 Main Steam Rad Monitor Ch. A1, B1 700 mR/hr 700 mR/hr Ch. A2, B2 700 mR/hr 700 mR/hr SJAE Off Gas Log Rad Monitor Ch. A, B 5 mR/hr 5 mR/hr Rx Bldg Vent.Ind/ Trip Unit Ch. A, B 0.6 mR/hr 0.6 mR/hr l l l 1 l l-1 . . .
L 1: 1989-EVALUATED EXERCISE Time z ~2005 Message Number: 9.11 ta ~02/05 , COOPER NUCLEAR STATION i EMERGENCY PREPAREDNE88 EXERCISE MESSAGE Hitssaae fort Emergency Director Simulated Plant Conditions! Messace
***THIS IS A DRILL ***
Declare a SITE AREA EMERGENCY in accordance with EPIP 5.7.1, l Attachment B, page 7 of 23, Initiating Condition 1.3.2, l
" Radiological gaseous effluent. releases resulting in THYROID dose '
rate at the site boundary of 125 Mrem /hr as determined by ADAM, i DOSE, hand calculations, or in-field surveys".
1989 EVALUATED EXERCISE Time z '2005 MESSAGE NUMBER: 9.1X tu *02/05 COOPER NUCLEAR STATION l EMERGENCY PREPAREDNESS EEERCISE NE88 AGE I FOR CONTROLLER.USE nNLYt controller Informations o Deliver this message only if a SITE AREA EMERGENCY has not ; been declared, and if there are no discussions in progress that will result in the declaration of an SITE AREA EMERGENCY. l l Expected Actions: 1 o See Message No. 7.1X " Expected Actions". l-1 i I l l i l L l
, , . , . .J
r 1989 EVALUATED EXERCISE Time = 3015_ ' Message Number: 10 t= 02/15 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE Messaae for: Control Room Simulated Plant Conditions: See attached Plant Data Message:
***THIS IS A DRILL ***
l l l-l l l l l
- ..y . . . , -
V l ' le 1989 EVALUATED EXERCISE Time = 2015 l
' MESSAGE NUMBER: 10 t= 02/15 COOPER NUCLEAR STATION l
EMERGENCY PREPAREDNESS EXERCISE MESSAGP j FOR CONTROT.TRR USE ONLY: 1 controller Information: Expected Actions: l l l
m L p-. l 1989 EVALUATED EXERCISE Time = 2015 Message Numbert 10 t= 02/15 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE PLANT DATA PANEL 9-3 PANEL 9- 5 . STATUS PRESS (psig) FIOW(gpm) REACTOR POWER 0% APRM RHR A STBY 50 0 REACTOR LEVEL 31 " NR RHR C STBY 50 REACTOR PRESSURE 1080 (psig) 6 RHR B SPC 240 7700 FLOW (10 lbs/hr) RHR D' STBY 50 FEEDWATER A 0.0 CS A' STBY 50 0 . FEEDWATER B 0.0 CS B STBY SO 0 MAIN STEAM A 0.0 HPCI TRIPPED 50 0 MAIN STEAM'B 0.0 Drywell Pressure 0.25 (psig) MAIN STEAM C 0.0 Torus Level 12.8 (feet) MAIN STEAM D 0.0 OPEN CLOEER CRD A FLOW 90 (gpm) MSIV 0 8 CRD B FLOW 90 (gpm) SLC LEVEL 75 % PANEL 9-4 SLC PMP DISCH PRESS A 0 SLC PMP DISCH PRESS B 0 STATUS PRESS (psig) FLOW (gpm) RCIC TRIPPED 50 0 RWCU A ISOI _ 0 0 MISCELLANEOUS PANELS RWCU B ISOL 0 0 RRP A 0 % SPD DIESEL GEN 1 STBY RRP B 0 % SPD DIESEL GEN 2 STBY SBGT A STBY SBGT B OPER DRYWELL COOLING ISOL TORUS WATER TEMP 83 F DRYWELL TEMP 116 Y
'1989 EVALUATED EXERCISE Time = 2015 Message: 10 COOPER NUCLEAR STATION t= 02/15 Q{ERGENCY PREPAREDNESS EXERCISE SPDS DATA Reactor Power (Avg % APRM) Reactor Level (in.)
+150 120
+100 100
+50 g w _
0 i' 60 50 40 20 l 150 0 j 30 15 0 30 15 0 1 Reactor Pressure (psig) 1200 1000 600 400 200 0
-30 15 0 Drywell Pressure (psig) Drywell Tenperature (OF )
300 75 250 60 200 45 150 30 100 15 50 0 0
-30 -15 0 -30 -15 0 Torus Level (in.) Torus Water Tenperature (OF )
+24 300 250
+12 200 0 150 100 12 50
-24 0 33 15 0 30 -15 0
"~
COOPER NUCLEAR STATION RADIATION MONITORS 1989 EVALUATED EXERCISE CLOCK TIME a 2015 SCENARIO TIME =-02/15 I STATION DESCRIPTION READING (mR/hr) i 1 Rx Bldg Fuel Pool Area (SE Sth Floor) 154 2 Ibc Bldg Fuel Pool Area (SE Sth Floor) 1.5
- 3. Rx Bldg New Fuel Area (SE 5th Floor) 0.3 l 1
4 Rx Bldg Rx Water Cleanup Domineralizar 113 Area (SW 3rd Floor) 5 Rx' Bldg Sludge and Decant Pump Area 0.8 (S 2nd Floor) 6 Rx Bldg Neutron Monitor System Index 164 Area (TIP Room ist Floor) 7 Rx Bldg Neutron Monitor System Drive 17 Mech Area (SE 1st Floor)
.8 Rx Bldg Control Rod Hydraulic Equipment 12 Area (S ist Floor) 9 Rx Bldg Control Rod Hydraulic Equipment 12 l
Area (N 1st Floor) 10 Rx Bldg HPCI Pump Room (SW Quad) 6 11 Rx Bldg RHR Pump Room (SW Quad) 70 12 Rx Bldg RHR Pump Room (NW Quad) 70 13 Rx Bldg RCIC/CS. Pump Room (NE Quad) 70 14 Rx Bldg CS Pump Room (SE Quad) 70 15 Turbine Bldg Turbine Front Standard 1 16 Turbine Bldg Mezz Control Corridor 0.2 17 Turbine Bldg Basement Control Corridor .05 18 Turbine Bldg Rx Feed Pump Area 6 19 Turbine Bldg Condensate Pump Area .12 20 Control Room Main Control Room .02 21- Grade Level Control Corridor ,19 22 Radwaste Centrol Room .03 23 Radwaste Pump Room 5 24 Radwaste Basement Equipment Area 4
- 25 Radwaste Domineralizer Valve Room 1.2 26 Radwaste Conveyor Aisle Operating Area _ _ _0 . 2 27 SPARE 28 Radwaste Lab Area .01 29 Centrifuge East 10 30 Centrifuge West 9 Panel 9-02 Personnel Airlock Area 903' 200 R/hr Panel 9-02 Ladder 903' to 2nd Level 200 R/hr OSH = Offscale High t
- 4
COOPER NUCLEAR STATION RADIATION MONITORS 1989 EVALUATED EXERCISE CLOCK TIME s 2015 SCENARIO TINE a 02/15
=======================================================================
PANEL VBDG Rx Bldg Vent Eff (RMV-RM-40) 1.OE-3 uCi/sec ERP Stack Normal Eff (RMP-RM-3A) 3.9E+4 uCi/sec ERP Stack High Range (RMP-RM-3B) 0- uci/see Turbine Bldg Vent Eff-(RMV-RM-20A) 1.5E-3 uCi/see Turbine Bldg High Range (RMV-RM-20B) o uC1/sec-RW/ARW Bldg Combined Eff (RMV-RM-30A) 1.0E-3 uCi/sec RW/ARW Bldg High Range (RMV-RM-30B) 0 uCi/sec EhHEL 9-10 Main Steam Rad Monitor Ch. A1, B1 400 mR/hr 400 mR/hr Ch. A2, B2 400 mR/hr 400 mR/hr
. SJAE Off Gas Log Rad Monitor Ch. A, B 1 mR/hr 1 mR/hr Rx Bldg Vent Ind/ Trip Unit Ch. A, B 0.6 mR/hr 0.6 mR/hr 1
.'= l l l 1 -
Time a 1989 EVALUATED EXERCISE 2030 Message Number 11__ tu 02/30 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE Massaae fort Control Roon simulated Plant Conditions: See attached Plant Data Messaget
***THIS IS A DRILL ***
Annunciators in the Control Room include:
~
AOG Trouble Alarm Indications in the Control Room include: AOG Steam Break Detection System AOG-30-113A,B,C, and D indicating lights lit AOG Steam Break Detection System AOG-30-114A,B,C, and D indicating lights illuminate a few seconds later L 1
1999 EVALUATED EXERCISE Time z 2030 MESSAGE NUMBER: _,11._ t= 02/30 COOPER. NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE FOR CONTROLLER USE ONLY Controller Informations o The steam jet air ejector steam supply line ruptures in the ARW building. ARW ventilation picks up this contaminated steam and discharges it to the environment via the ARW Building Ventilation. The release is now considered a ground level, unfiltered, monitored release. Expected Actions o Emergency Director declare a GENERAL EMERGENCY per EPIP 5.7.1, Attachment B, page 7 of 23, Initiating Condition 1.4.2,
" Radiological gaseous effluent releases resulting in THYROID dose Inta at the site boundary of 5 Rom /hr using actual Met, conditions as determined by ADAM, DOSE, hand calculations, or in-field survevs".
e o Emergency Director implement EPIP 5.7.3, " GENERAL EMERGENCY" . l l
k 1 1989 EVALUATED EXERCISE' Time = 2030 Message Number . 11 t= 02/30 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE PLANT DATA PANEL 9-3 PANEL 9-5 STATUS PRESS (psig) FLOW (gpm) REACTOR POWER 0% APRM RHR A STBY 50 0 REACTOR LEVEL 31 " NR
- RHR C STBY 50 REACTOR PRESSURE 1040 (psig) 8 RRR B SPC 240 7700 ELQW (10 lbs/hr)
A B 0 FE WA RB .0 CSL B ' STBY 50 0 MAIN STEAM A 0.0 HPCI TRIPPED 50 0 MAIN STEAM B 0.0 Drywell Pressure 0.25 (psig) MAIN STEAM C 0.0 Torus Level 12,8 (feet) MAIN STEAM D 0.0 OPEN CLOSED CRD A FLOW 90 (gpm) MSIV O 8 CRD B FLOW 90 (gpm) l; SLC LEVEL 75 % PANEL 9-4 SLC PMP DISCH PRESS A 0 l SLC PMP DISCH PRESS B 0 L STATUS PRESS (psig) FLOW (gpm) RCIC' TRIPPED 50 0 L RWCU'A ISOL 0 0 MISCELLANEOUS PANELS I l RWCU B ISOL 0 0
. RRP A 0 % SPD DIESEL GEN 1 STBY 1
l RRP B 0 % SPD DIESEL GEN 2 STBY SBGT A STBY SBGT B OPER DRYWELL COOLING ISOL l TORUS WATER TEMP 84 Y DRYWELL TEMP 118 T
~. . , _ _ - - ,
4 1989 EVALUATED. EXERCISE Time = 2030 y Maanage: 11 COOPER NUCLEAR STATION t= O2/30 EMERGENCY PREPAREDNESS EXERCISE SPDS DATA Reactor Power (Avg 1 APRM) Reactor Levet (in.)
+150 120
+100 100
+50 80 0 ?
60 50 40 100 20 150 0 30 15 0 30 15 0 t Reactor Pressure (psig) 1200 1000
?
800 600 400 200 0 30- 15 0 DryweLL Pressure (psig) Drywell Tenperature (OF ) 300 75 250 60 200 45 150 30 100 15 50 0 0 30 15 0 10 15 0 Torus Level (in.) forus Water Tenperature (OF )
+24 300 250
+12 200 0 150 100
-12 ,
50 1 24 0 15 0 30 -15 0 30
.1: -
o l COOPER NUCLSAR STATION RADIATION MONITORS 1989 EVALUATED EXERCISE CLOCE TIME a 2030 SCENARIO TIME = 02/30
===================================================================
STATION DESCRIPTION READING (mR/hr) 1 Rx Bldg Fuel Poul Area (SE 5th Floor) 154 2 Rx Bldg Puel Pool Area (SE Sth Floor) 1.5 3 Rx Bldg New Fuel Area (SE 5th Floor) __. 0.3 4 Rx Bldg Rx Water Cleanup Demineralizar , 113 Area (SW 3rd Floor) 5 Rx Bldg Sludge and Decant Pump Area __ 0.8 (S 2nd Floor) 6 Rx Bldg Neutron Monitor System Index 164 Area (TIP Room ist Floor) 7 Rx Bldg Neutron Monitor System Drive 13 Mech Area (SE ist Floor) 8 Rx Bldg Control Rod Hydraulic Equipment 9 Area (S 1st Floor) 9 Rx Bldg Control Rod Hydraulic Equipment 9 Area (N ist Floor) 10 Rx Bldg HPCI Pump Room (SW Quad) 7 11 Rx Bldg RHR Pump Room (SW Quad) 70 12 Rx Bldg RHR Pump Room (NW Quad) 70 13 Rx Bldg RCIC/CS Pump Room (NE Quad) 70 14 Rx Bldg CS Pump Room (SE Quad) 70 15 Turbine Bldg Turbine Front Standard i 16 Turbine Bldg Mezz Control Corridor 0.2 17 Turbine Bldg Basement Control Corridor .05 18 Turbine Bldg Rx Feed Pump Area 1 19 Turbine Bldg Condensate Pump Area .12 20 Control Room Main Control Room .02 21 Grade Level Control Corridor .19 22 Radwaste Control Room .03 23 Radwaste Pump Room 5 24 Radwaste Basement Equipment Area 4 25 Radwaste Domineralizar Valve Room 1.2 26 Radwaste Conveyor Aisle Operating Area 0.2 27 SPARE 28 Radwaste Lab Area .01 29 Centrifuge East 10 30 Centrifuge West . 9 Panel 9-02 Personnel Airlock Area 903' 180 R/hr Panel 9-02 Ladder 903' to 2nd Level 180 R/hr 4 OSH = Offscale High
i l J COOPER NUCLEAR STATION RADIATION NOMITORS 1989 EVALUATED EXERCISE CLOCK TIME = 2030 SCENARIO TIME a 02/30 )
..............................m........................................ :
l PANEL VBDG ! Rx Bldg Vent Eff (RMV-RM-40) 1.0E-3 uci/see ERP Stack Normal Eff (RMP-RM-3A) 1.0E-3 uci/see ] ERP Stack High Range (RMP-RM-3B) o uci/see l Turbine Bldg Vent Eff (RMV-RM-20A) 1.5E-3 uci/see Turbine Bldg High Range (RMV-RM-20B) o uci/see RW/ARW Bldg Combined Eff (RMV-RM-30A) 1.0E+6 uCi/see RW/ARW Bldg High Range (RMV-RM-308) o uci/see PANEL 9-10 Main Steam Rad Monitor Ch. A1, B1 300 mR/hr 300 mR/hr Ch. A2, B2 300 mR/hr 300 mR/hr SJAE Off Gas Log Rad Monitor Ch. A, B 1 mR/hr 1 mR/hr Rx Bldg Vent Ind/ Trip Unit Ch. A, B 0.6 mR/hr 0.6 mR/hr i
~
1989 EVAMATED EXERCISE Time = '2045 Message Number: 11.1X t = *02/45 COOPER NUCLEAR STATION ! EMERGENCY PREPAREDNESS EXERCISE MESSAGE i Messaae for: Emergency Director , Simulated Plant Conditions. Messagg:
***THIS IS A DRILL *** ;
Declare a GENERAL EMERGENCY in accordance with EPIP 5.7.1, Attachment B, page 7 of 23, Initiating Condition 1.4.2, " Radiological gaseous effluent releases resulting in Intearated THYROID dose Droiection at the site boundary of 5 Rem using actual Met. conditions as determined by ADAM, DOSE, hand calculations, or . in-field surveys".
,- + - - - , , - ._ - - - -
i l i 1980 EVALUATED EXERCISE , Time z *2045_ ! MESSAGE NUMBERt 11.1X tx *02/45 ! COOPER NUCLEAR STATION ENERGENCY PREPAREDNESS... EXERCISE MESSAGE E91LQ9EIB93MJL.DH_9EX1 Controller Information: o Deliver this message only if a GENERAL EMERGENCY has not been declared, and if there are no discussions in progress that will result in the declaration of an GENERAL EMERGENCY. ; Expected Actions: o See Massage No. 11 " Expected Actions". t
1989 EVALUATED EXERCISE Time = -2045 i Message Number: 12 t= 02/45 COOPER NUCLEAR STATION EMERGENCY... PRE PAREDNES S .. EXERCI S E ..MES S AGE Messaae fort control Room Simulated Plant Conditions: See attached Plant Data Messaget
***THIS IS A DRILL ***
1989 EVAIAJATED EXERCISE Time = 2045 MESSAGE NUMBER: 12 t= 02/45, COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE FOR CONTROT Y 5'R USE ONLY: Controller Information: Expected Actions: a g
i l 1989 EVALUATED EXERCISE Time = 2045 Message Numbert _11_ t= 02/45 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE PLANT DATA PANEL 9-3 PANEL 9-5 STATUS PRESS (psig) FLOW (gpm) REACTOR POWER 0% APRM RHR A STBY 50 0 REACTOR LEVEL 31 " _ER_ RRR C STBY 50 REACTOR PRESSURE 1000 (psig) SPC 7700 s RHR B 240 FLOW (lo lbs/hr) RHR D STBY 50 FEEDWATER A 0.0 CS A STBY 50 0 TEEDWATER B 0.0 CS B __EIR1_ 50 0 MAIN STEAM A 0.0 HPCI TRIPPED 50 0 MAIN STEAM B 0.0 Drywell Pressure 0.25 (psig) MAIN STEAM C 0.0 Torus Level 12.8 (feet) MAIN STEAM D 0.0 OPEN CLOSED CRD A FLOW 90 (gpm) MSIV O 8 CRD B FLOW 90 (gpm) SLC LEVEL 7 5_ __ % PANEL 9-4 SLC PMP DISCH PRESS A 0 SLC PMP DISCH PRESS B 0 STATUS PRESS (psig) FLOW (gpm) RCIC TRIPPED 50 0 RWCU A ISOL 0 0 MISCELLANEOUS PANELS RWCU B ISOL 0 0 RRP A 0 % SPD DIESEL GEN 1 STBY RRP B 0 % SPD DIESEL GEN 2 STBY SBGT A STBY SBGT B OPER DRYWELL COOLING ISOL TORUS WATER TEMP 85 T DRYWELL TEMP 120 Y l l l l
> l 1 j._ l i f 1989 EVALUATED EXERCISE Time = 2045 i i Message: _ 12 COOPER NUCTRAR STATION t = _02/45 l i EMERGENCY PREPAREDNESS EXERCISE SPDS DATA ) I l teactor Power (Avg % U RM) Reactor tevel (in.) ;
- +150 I 120 l
+100 l 100 i
+50 j 80 l 0 1 60 l 50 l 40 l 100 )
150 0 30 15 0 30 15 0 Reactor Pressure (psig) 1200 1000 600 400 200 0 30 15 0 OryweLL Pressure (psig) Orywell Tag erature ('F) 300 75 250 60 200 45 150 30 100 15 50 0 0 30 15 0 10 15 0 forus Level (in.) f orun Water temerature (07 )
+24 300 250
+12 200 0 150 100 12 50 24 0 30 15 0 50 15 0
p i i COOPER NUCLEAR STATION ' RADIATION NONITORS 1989 EVALUATED EXERCISE CLOCK TIME a 2045 SCENARIO TIME = 02/45
===================================================================
STATION DESCRIPTION READING (mR/hr) 1 Rx Bldg Fuel Pool Area (SE Sth Floor) 154 2 Rx Bldg Fuel Pool Area (SE Sth Floor) 1.5 3 Rx Bldg New Fuel Area (SE 5th Floor) 0.3 4 Rx Bldg Rx Water Cleanup Domineralizer 113 Area (SW 3rd Floor) 5 Rx Bldg Sludge and Decant Pump Area 0.8 (S 2nd Floor) 6 Rx Bldg Neutron Monitor System Index 164 l Area (TIP Room ist Floor) 1 7 Rx Bldg Neutron Monitor System Drive 10 Mech Area (SE 1st Floor) , 8 Rx Bldg Control Rod Hydraulic Equipment 6 Area (S ist Floor) 9 Rx Bldg Control Rod Hydraulic Equipment 9 Area (N ist Floor) 10 Rx Bldg HPCI Pump Room (SW Quad) 7 11 Rx Bldg RHR Pump Room (SW Quad) 80 12 Rx Bldg RHR Pump Room . (IM Quad) 80 13 Rx Bldg RCIC/CS Pump Room (NE Quad) 80 14 Rx Bldg CS Pump Room (SE Quad) 80 15 Turbine Bldg Turbine Front Standard 1 _ 16 Turbine Bldg Metz Control Corridor 0.2 17 Turbine Bldg Basement Control Corridor .05 18 Turbine Bldg Rx Feed Pump Area 1 19 Turbine Bldg Condensate Pump Area .12 20 Control Room Main Control Room .02 21 Grade Level Control Corridor .19 22 Radwaste Control Room .03 23 Radwaste Pump Room 5 ; 24 Radwaste Basement Equipment Area 4 ! 25 Radwaste Demineralizer Valve Room 1.2 l 26 Radwaste Conveyor Aisle Operating Area 0.2 I 27 SPARE 28 Radwaste Lab Area ___
.01 l 29 Centrifuge East 10 )
30 Centrifuge West 9 I I Panel 9-02 Personnel Airlock Area 903' 80 R/hr Panel 9-02 Ladder 903' to 2nd Level 80 R/hr OSH = Offscale High l l
i COOPER NUCLEAR STATION ' RADIATION NONITORS 1989 EVALUATED EXERCISE CLOCK TIME a 2045 SCENARIO TIME a 02/45 PANEL VBDG Rx Bldg Vent Eff (RMV-RM-40) 1.0E-3 uCi/see f ERP Stack Normal Eff (RMP-RM-3A) 1.0E-3 uCi/see ERP Stack High Range (RMF-RM-3B) o uci/see Turbine Bldg Vent Eff (RMV-RM-20A) 1.5E-3 uCi/see Turbine Bldg High Range (RMV-RM-20B) o uCi/see RW/ARW Bldg Combined Eff (RMV-RM-30A) 9.2E+5 uCi/sec RW/ARW Bldg High Range (RMV-RM-30B) 0 uCi/see i PANEL 9-10 Main Steam Rad Monitor Ch. Al, El 150 mR/hr 150 mR/hr Ch. A2, B2 150 mR/hr 150 mR/hr SJAE Off Gas Log Rad Monitor Ch. A, B 1 mR/hr 1 mR/hr 0.6 mR/hr 0.6 mR/hr ] Rx Bldg Vent Ind/ Trip Unit Ch. A, B 4 1 I 1 i
'n--- 2
,r
. 1989 EVAIDATED EXERCISE Time = 2100 Message Number: 13 t= 03/00 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE Messaae for: Control Room simulated Plant Conditions: See attached Plant Data Message:
***THIS IS A DRILL ***
, 1 I l l l l i l
r , I I
\
1989 EVALUATED EXERCISE Time = 2100 l MESSAGE NUMBER: 1 t= 03/00 j l COOPER NUCLEAR STATION l l EMERGENCY PREPAREDNESS EXERCISE MESSAGE l
)
FOR CONTROTTRR USE ONLY: ] Controller Information: l 1 Expected Actions: l
i b 1989 EVALUATED EXERCISE Time a 2100 Message Number _13_ t a _03/00 COOPER NUCLEAR STATION ; EMERGENCY PREPAREDNESS EXERCISE PLANT DATA l t PANEL 9-3 PANEL 9-5 STATUS PRESE(psig) ELQH(gpm) REACTOR POWER 0% AfBd RHR A STBY 50 0 REACTOR LEVEL 31 " _HE_ RHR C STBY 50 REACTOR PRESSURE 950 (psig) RHR B SPC 240 7700 ELQH (los lbs/hr) R3R D STBY 50 FEEDWATER A 0.0 CS A STBY 50 0 FEEDWATER B 0.0 CS B STBY 50 0 MAIN STEAM A 0.0 HPCI TRIPPED 50 0 MAIN STEAM B 0.0 Drywell Pressure 0.25 (psig) MAIN STEAM C 0.0 Torus Level 12.9 (feet) MAIN STEAM D 0.0 QEEE CLOSED CRD A FLOW 90 (gpm) MSIV O 8 CRD B FLOW 90 (gpm) SLC LEVEL 75 % PANEL 9-4 SLC PMP DISCH PRESS A 0 SLC PMP DISCH PRESS D 0 STATUS PRESS (psig) FLOW (gpm) RCIC TRIPPED 50 0 RWCU A ISOL 0 0 MISCELLANEOUS PANELS RWCU B ISOL 0 0 RRP A 0 % SPD DIESEL GEN 1 STBY RRP B 0 % SPD DIESEL GEN 2 STBY SBGT A STBY SBGT B OPER L i ! DRYWELL COOLING ISOL TORUS WATER TEMP 85 9F DRYWELL TEMP 120 9F
6 i 1989 EVALUATED EXERCISE Time = _2100 ; Message: 13 COOPER NUCLEAR STATION t= 03/00 EMERGENCY PREPAREDNESS EXERCISE SPDS DATA Reatter Power (Avg % APRM) Raattor Level (in.)
+150 120
+100 100
+50 80 0
60 1 50 40 100 20 150 0 30 15 0 30 15 0 Reactor Pressure (psiO ) 1200 1000 800 600 400 200 ; O 30 15 0 Drywell Pressure (psig) Drywell temperature ('F) 300 75 250 60 200 45 150 30 100 15 50 0 0 , 30 15 0 30 15 0 f orus Level (in.) Tocus Water Temperature ('f)
+24 300 250
+12 200 0 150 100 12 50 24 0 30 15 0 30 15 0
t COOPER NUCLEAR STATION RADIATION MONITORS 1989 EVALUATED EEERCISE CLOCK TIME = 2100 SCENARIO TIME = 03/00
=======================================================
P STATION DESCRIPTION READIl!G (mR/hr) 1 Rx Bldg Fuel Pool Area (SE 5th Floor) 154 ' 2 Rx Bldg Fuel Pool Area (SE 5th Floor) 1.5 , 3 Rx Bldg New Fuel Area (SE 5th Floor) 0.3 4 Rx Bldg Rx Water Cleanup Domineralizer 113 Area (SW 3rd Floor) i 5 Rx Bldg Sludge and Decant Pump Area 0.8 (S 2nd Floor) 6 Rx Bldg Neutron Monitor System Index 164 Area (TIP Room ist Floor) 1 7 Rx Bldg Neutron Monitor System Drive 8 Mach Area (SE 1st Floor) B Rx Bldg Control Rod Hydraulic Equipment 7 Area (S ist Floor) 9 Rx Bldg Control Rod Hydraulic Equipment 9 Area (N ist Floor) 10 Rx Bldg HPCI Pump Room (SW Quad) 8 ; 11 Rx Eldg RHR Pump Room (SW Quad) 80 12 Rx Bldg RHR Pump Room (NW Quad) 80 13 Rx Bldg RCIC/CS Pump Room (NE Quad) 80 14 Rx Bldg CS Pump Room (SE Quad) 80 : 15 Turbine Bldg Turbine Front Standard i 16 Turbine Bldg Mezz Control Corridor 0.2 17 Turbine Bldg Basement Control Corridor .05 18 Turbine Bldg Rx Feed Pump Area 1 19 Turbine Bldg Condensate Pump Area .12 20 Control Room Main Control Room .02 21 Grade Level Control Corridor .19 22 Radwaste Control Room .03 _ 23 Radwaste Pump Room 5 24 Radwaste Basement Equipment Area 4 25 Radwaste Domineralizar Valve Room 1.2 26 Radwaste Conveyor Aisle Operating Area 0.2 27 SPARE 28 Radwaste Lab Area .01 29 Centrifuge East 10 30 Centrifuge West 9 Panel 9-02 Personnel Airlock Area 903' 40 R/hr Panel 9-02 Ladder 903' to 2nd Level 40 R/hr OSH = Offscale High
COOPER NUCLEAR STATION + RADIATION MONITORS : 1989 EVALUATED EXERCISE CLOCK TIME a 2100 SCENARIO TIME a 03/00
===========================================================
PANEL VBDG Rx Bldg Vent Eff (RMV-RM-40) 1.0E-3 uci/see ERP Stack Nornal Eff (RMP-RM-3A) 1.0E-3 uci/see ERP Stack High Range (RMP-RM-3B) o uci/see Turbine Bldg Vent Eff (RMV-RM-20A) 1.5E-3 uCi/see Turbine Bldg Migh Range (RMV-RM-20B) o uti/see RW/ARW Bldg Combined Eff (RMV-RM-30A) 8.6E+5 uci/see RW/ARW Bldg Migh Range (RMV-RM-30B) 0 uci/see PANEL 9-10 Main Steam Rad Monitor Ch. A1, B1 100 mR/hr 100 mR/hr Ch. A2, B2 100 mR/hr 100 mR/hr SJAE off Gas Log Rad Monitor Ch. A, B 1 mR/hr 1 mR/hr , Rx Bldg Vent Ind/ Trip Unit Ch. A, B 0.6 mR/hr 0.6 mR/hr e j W w r,r ,,w ~ - - - - m-
i 1989 EVALUATED EXERCISE Time = 2115 Message Number: 14 t= 03/15 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE t Messaae for: Control Room Simulated Plant conditions:. See attached Plant Data Message:
***THIS IS A DRILL ***
i
I 1989 EVALUATED EEERCISE Time a 2115 MESSAGE WUMBER: 1 ts 03/15 COOPER NUCLEAR STATION . EMERGENCY PREPAREDNESS EEERCISE MESSAGE FOR CONTROLLER USE ONLYt controller Information , o With SRVs restored, operators emergency depressurize, this i essentially terminates the release, o Operators control and restore reactor water level using the : condensate booster pumps or other low pressure pumps. Expected Actiones l o Emergency depressurize the reactor. s 5
1989 EVALUATED EEERCISE Time a 2115 Wessage Numbert .31 t= 03/15 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EEERCISE PLANT DATA PANEL 9-3 PANEL 9-5 STATUS PRESS (psig) ELQM(gpm) REACTOR POWER 0 _% Mg RHR A STBY 50 0 REACTOR LEVEL ,_11 " lf}L RHR C STBY 50 REACTOR PRESSURE 880 (psig) RHR B SPC 240 7700 ILQH (106 lbs/hr) RHR D STBY 50 FEEDWATER A 0.0 CS A STBY 50 O FEEDWATER B 0.0 CS B STBY 50 0 MAIN STEAM A 0.0 HPCI TRIPPED 50 0 MAIN STEAM B 0.0 Drywell Pressure h.2.5 (psig) MAIN STEAM C 0.0 Torus Level 12_d (f eet) MAIN STEAM D 0.0 QEEl{ CLOSED CRD A FLOW 90 (gpm) MSIV O 8 CRD B FLOW 90 (gpm) SLC LEVEL 75 % PANEL 9-4 SLC PMP DISCH PRESS A 0 SLC PMP DISCH PRESS B 0 STATUS PRESS (psig) ELQM(gpm) RCIC TRIPPED 50 0 RWCU A ISOL 0 0 MISCELLANEOUS PANELS RWCU B ISOL 0 0 RRP A _ 0 % SPD DIESEL GEN 1 STBY RRP B o % SPD DIESEL GEN 2 STBY SBGT A STBY SBGT B OPER DRYWELL COOLING ISOL TORUS WATER TEMP 85 F DRYWELL TEMP 120 F
a . 1989 EVALUATED EXERCISE Time = 2115 3 Message: 14 COOPER NUCLEAR STATION t= 03/15 EMERGENCY PREPAREDNESS EXERCISE SPDS DATA teactor Power ( Ave
- APR=) teactor Levet (in.)
+150 120
+100 100 '
+50 40 0
60 50 40 100 , 20 150 0 -- 30 15 0 30 15 0 teactor Pressure (gs10) 1200 1000 800 600 4 00 200 , 0
-30 15 0 ,
DryweLL Pressure (psig) Drywell f enperature ('f) 300 75 250 60 200 45 150 30 100 15 50
- 0 0
30 15 0 +30 +15 0 forus Level (in.) f orus Water tagerature ('f)
+24 300 250
+12 200 0 150 100 12 50 24 0 30 15 0 30 15 0
k COOPER NUCLEAR STATION RADIATION MONITORS 1989 EVALUATED EEERCISE CLOCE TIME a 2115 SCENARIO TIME = 03/15
===================================================================
STATION DESCRIPTION READING (mR/hr) 1 Rx Bldg Fuel Pool Area (SE Sth Floor) 154 2 Rx Bldg Puel Pool Area (SE Sth Floor) 1.5 - 3 Rx Bldg New Fuel Area (SE 5th Floor) 0.3 4 Rx Bldg Rx Water Cleanup Domineralizer 113 , Area (SW 3rd Floor) 5 Rx Bldg Sludge and Decant Punp Area 0.8 (S 2nd Floor) 6 Rx Bldg Neutron Monitor System Index 164 Area (TIP Room ist Floor) 7 Rx Bldg Neutron Monitor System Drive 2 Mech Area (SE 1st Floor) 8 Rx Bldg Control Rod Hydraulic Equipment i Area (S ist Floor) 9 Rx Bldg Control Rod Hydraulic Equipment 9 Area (N 1st Floor) 10 Rx. Bldg HPCI Pump Room (SW Quad) 8 11 Rx Bldg RHR Pump Room (SW Quad) 120 12 Rx Bldg RHR Pump Room (NW Quad) 120 13 Rx Bldg RCIC/CS Pump Room (NE Quad) 120 ' 14 Rx Bldg CS Pump Room (SE Quad) 120 15 Turbine Bldg Turbine Front Standard 1 16 Turbine Bldg Mezz Control Corridor 0.2 . 17 Turbine Bldg Basement Control Corridor .05 18 Turbine Bldg Rx Feed Pump Area 1 19 Turbine Bldg Condensate Pump Area .12 20 Control Room Main Control Room .02 21 Grade Level Control Corridor .19 22 Radwaste Control Room .03 21 Radwaste Pump Room 5 24 Radwaste Basement Equipment Area 4 25 Radwaste Domineralizer Valve Room 1.2 26 Radwaste Conveyor Aisle Operating Area 0.2 27 SPARE 28 Radwaste Lab Area .01 29 Centrifuge East 10 30 Centrifuge West 9 Panel 9-02 Personnel Airlock Area 903' 20 R/hr Panel 9-02 Ladder 903' to 2nd Level __ H2O R/hr , OSH = Offscale High I
i l I C00PER WUCLEAR STATION RADIATION NONITORS 1989 EVALUATED EEERCISE CLOCK TIME a 2115 I 8CENARIO TIME a 03/15 maammmmmmmmmmmmmmmmmmmmmmmmma?smammmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmma PANEL VBDG Rx Bldg Vent Off (RMV-RM-40) 1.0E-3 uCi/see i ERP Stack Normal Eff (RMP-RM-3A) 1.0E-3 uCi/see l ERP Stack High Range (RMP-RM-3B) o uCi/see ! Turbine Bldg Vent Eff (RMV-RM-20A) 1.5E-3 uci/see Turbine Bldg High Range (RMV-RM-20B) __0 uci/see RW/ARW Bldg Combined Eff (RMV-RM-30A) _p.oE+2 uci/see , . RW/ARW Bldg High Range (RMV-RM-30B) o uCi/see I PANEL 9-10 Main Steam Rad Monitor Ch. A1, B1 70 mR/hr 70 mR/hr Ch. A2, B2 70 mR/hr 70 mR/hr SJAE Off Gas Log Rad Monitor Ch. A, B 1 mR/hr 1 mR/hr Rx Bldg Vent Ind/ Trip Unit Ch. A, B 0.6 mR/hr 0.6 mR/hr
i 1989 EVALUATED EXERCISE Time = 2130 Message Number: 15 t= 03/30 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE Messaae fort Control Room glaulated__ Plant Conditions: See attached Plant Data Messages
*** TRIS IS A DRILL ***
Indications in the control Room include: HPCI MO-15 Inboard Isolation Valve, Green light energized 6
i I i I 1989 EVALUATED EXERCISE Time = 2130 l MESSAGE UUMBER _11_ t= 03/30 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS... EXERCISE _ MESSAGE 1 l FOR CONTROLLER USE ONLY Controller Informatient ! I o Deliver the message cover sheet when word is received from the ; OSC controllers that the breaker for the HPCI inboard i isolation valve has been repaired. See SS$1. Expected Actionst o Isolate HPCI, inform the other ERTs. ; P e * *
- i 1989 EVALUATED EXERCISE Timo = 2130 i Messago: 15 COOPER NUCLEAR STATION t= 03/30 EMERGENCY.. PREPAREDNESS. EXERCISE SPDS DATA teacte.r Power (Avg 1 APM ) Reactor tevel (In.) ',
+150 120
+100 ,
100 1
+50 60 60 l 50 ,
40 100 20 150 0 30 15 0 30 15 0 Reactor Pressure (psig) 1200 1000 , 800 600
's 4 00 200
~
30 15 0 DryweLL Pressure (psig) Drywelt Tenperature ('F) 300 75 250 60 200 45 150 30 100 15 50 0 0 30 15 0 30 15 0 f orus level (in.) forus Water Tecperature (DF )
+24 300 250
+12 200 f
0 150 100 12 50 24 0 30 15 0 30 15 0
~
V I 1989 EVALUATED EXERCISE Time a 2130 : Message Number _11_ t= 03/30 l , COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE PLANT DATA # PANEL 9-3 PANEL 9-5 STATUS PRESS (psig) FLOW (gpm) REACTOR POWER 04 AEgg RHR A STBL_ 50 0 REACTOR LEVEL 45 " _HE_ RHR C STBY 50 REACTOR PRESSURE 60 (psig) 6 RHR B SPC 240 7700 FLOW (10 lbs/hr) , RHR D STBY 50 FEEDWATER A 0.0 CS A STBY 50 0 FEEDWATER B 0.0 ' CS B STBY 50 0 MAIN STEAM A 0.0 HPCI TRIPPED 50 0 MAIN STEAM B 0.0 Drywell Pressure D225 (psig) MAIN STEAM C 0.0 Torus Level 1111 (feet) MAIN STEAM D 0.0 OPEN CLOSED CRD A FLOW 90 (gpm) MSIV 0 8 CRD B FLOW 90 (gpm) SLC LEVEL 75 % PANEL 9-4 SLC PMP DISCH TRESS A 0 SLC PMP DISch PRESS B 0 STATUS PRESS (psig) flQM(gpm) RCIC TRIPPED 50 0 RWCU A ISOL 0 0 MISCELLANEOUS PANELS RWCU B ISOL 0 0 RRP A 0 % SPD DIESEL GEN 1 STBY RRP B 0 % SPD DIESEL GEN 2 STBY SBGT A STBY SBGT B OPER DRYWELL COOLING ISOL TORUS WATER TEMP 92 9F DRYWELL TEMP 122 EP
COOPER NUCLEAR STATION RADIATION NONITORS 1989 EVALUATED EXERCISE CLOCK TIME a 2130 SCENARIO TIME = 03/30
===================================================================
STATION DESCRIPTION READING (mR/hri 1 Rx Bldg Fuel Pool Area (SE 5th Floor) 154 2 Rx Bldg Fuel Pool Area (SE Sth Floor) 1.5 3 Rx Bldg New Fuel Area (SE Sth Floor) 0.3 4 Rx Bldg Rx Water Cleanup Domineralizer 113 Area (SW 3rd Floor) 5 Rx Bldg Sludge and Decant Pump Area 0.8 (S 2nd Floor) 6 RX Bldg Neutron Monitor System Index 164 Area (TIP Room ist Floor) 7 Rx Bldg Neutron Monitor System Drive 1.8 Mech Area (SE 1st Floor)
- 8 Rx Bldg Control Rod Hydraulic Equipment 0.9 Area (S 1st Floor) 9 Rx Bldg Control Rod Hydraulic Equipment _ 9 Area (N 1st Floor) 10 Rx Bldg HPCI Pump Room (SW Quad) 12 11 Rx Bldg RHR Pump Room (SW Quad) 250 12 Rx Bldg RHR Pump Room (NW Quad) 250 13 Rx Bldg RCIC/CS Pump Room (NE Quad) 250 14 Rx Bldg CS Pump Room (SE Quad) 250 15 Turbine Bldg Turbine Front Standard 1 16 Turbine Bldg Mezz Control Corridor 0.2 17 Turbine Bldg Basement Control Corridor .05 18 Turbine Bldg Rx Feed Pump Area 1 19 Turbine Bldg Condensate Pump Area .12 __
20 Control Room Main Control Room _ .02 21 Grade Level Control Corridor .19 22 Radwaste Control Room .03 23 Radwaste Pump Room 5 24 Radwaste Basement Equipment Area __ 4 25 Radwaste Domineralizer Valve Room 1.2 26 Radwaste Conveyor Aisle operating Area 0.2 27 SPARE 28 Radwaste Lab Area .01 29 Centrifuge East 10 30 Centrifuge West 9 Panel 9-02 Personnel Airlock Area 903' 20 R/hr Panel 9-02 Ladder 903' to 2nd Level 20 R/hr OSH = Offscale High
i I 1 1 e l COOPER NUCLEAR STATION ! RADIATION NONITORS l 1989 EVALUATED EEERCISE CLOCK TIME a 2130 i SCENARIO TIME = 03/30 1 PANEL VBDG 1 Rx Bldg Vent Ef f (RMV-T 1-40) 1.0E-3 uci/see ERP Stack Normal Eff (RMP-RM-3A) 1.0E-3 uci/see ERP Stack High Range (RMP-RM-3B) o uci/see , I Turbine Bldg Vent Eff (RMV-RM-20A) 1.5E-3 uci/see Turbine Bldg High Range (RMV-RM-20B) o uci/see , RW/ARW Bldg Combined Eff (RMV-RM-30A) 6.5E-2 uCi/see RW/ARW Bldg High Range (RMV-RM-30B) 0 uci/see PANEL 9-10 Main Steam Rad Monitor Ch. A1, B1 25 nR/hr 25 mR/hr Ch. A2, B2 25 MRLhr; 25 mR/hr ! SJAE Off G4.s Log Rad Monitor Ch. A, B 1_mR/hr 1 mR/hr Rx Bldg Vent Ind/ Trip Unit Ch. A, B 0.6 mR/hg_0.6 mR/hr e *
.c -
1989 EVALUATED EXERCISE Time = 2145 Message Number: 16 t= 03/45 COOPER NUCLEAR STATION-EMERGENCY PREPAREDNESS EXERCISE MESSAGE Messaae for: Control Room Simulated Plant Conditions: See attached Plant Data Hansage:
***THIS IS A DRILL ***
1989 EVALUATED EXERCISE Time = 2145 MESSAGE NUMBER: 16 t= 03/45 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE FOR CONTROT.T.RR USE ONLY: Controller Information: Expected Actiona: i
< I 1949 EVALUATED EXERCISE Time a 2145
. Message Number! _11_ tx 03/45 COOPER NUCLEAR STATION EMERGENCY PREPAREDNES8 EXERCI8E PLANT DATA PANEL 9-3 PANEL 9-5 STATUS PRESS (psig) FLOW (gpm) REACTOR POWER 0% APRM
- RHR A STBY 50 0 REACTOR LEVEL 45 " _ ER_
RHR C __STBY 50 REACTOR PRESSURE 70 (psig) 6 RHR B SPC 240 7700 f,LQW (10 lbs/hr) RHR D- STBY 50 FEEDWATER A 0.0 CS A STBY 50 0 FEEDWATER B 0.0 CS B STBY SO 0 MAIN STEAM A 0.0 L HPCI TRIPPED. 50 0 MAIN STEAM B 0.0 Drywell Pressure 0.25 (psig) MAIN STEAM C 0.0 Torus Level 13.1 (feet) MAIN STEAM D 0.0 OPEN CLOSED CRD A FLOW 50 (gpm) MSIV O 8_ CRD B FLOW 50 (gpm) L l SLC LEVEL 75 % PANEL 9-4 SLC PMP DISCH PRESS A 0 SLC PMP DISCH PRESS B 0 STATUS PRESS (psig) FLOW (gpm) RCIC TRIPPED 50 0 RWCU A ISOL 0 0 MISCELLANEOUS PANELS RWCU B ISOL 0 0 l RRP A 0 % SPD DIESEL GEN 1 STBY RRP.B 0 % SPD DIESEL GEN 2 STBY SBGT A STBY SBGT B OPER DRYWELL COOLING ISOL TORUS WATER TEMP 91 9P DRYWELL TEMP 122 9P 6FN E
- g *]*4%$ % N e"$43i- W ,F=+ '
e 1989 EVALUATED EXERCISE Time = 2145 Message: 16 COOPER NUCLEAR STATION t = _03/45 EMERGENCY PREPAREDNESS EXERCISE SPDS DATA Reactor Power ( Avg % APitM) Reactor Level ( n.)
+150 120
+100 100
+50 0
60 50 40 100 20 150 0 - 30 'S 0 30 15 0 Reactor Pressure (psig) 1200 1000 800 600 400 200
~%-
30 15 0 Drywell Pressure (pulg) Drywell Tenperature (OF ) 300 75 250 60 200 45 150 30 - 100 15 50 0 0 30 15 0 30 15 0 Torus Level (in.) Torus Water Tenperature (OF )
+24 300 250
+12 200 0 150 100
-12 '
50 .
-24 0
-30 15 0 30 15 0
I l I COOPER NUCLEAR STATION l RADIATION MONITORS I
.1989 EVALUATED EXERCISE CLOCK TIME a 2145 l SCENARIO TIME = 03/45 l STATION DESCRIPTION READING (mR/hr) 1 Rx Bldg Fuel-Pool Area (SE 5th Floor) 154 2 Rx Bldg-Fuel Pool Area (SE Sth Floor) 1.5 3 Rx Bldg New Fuel Area (SE 5th Floor) 0.3 4 Ex Bldg Rx Water Cleanup Demineralizer 113 Area (SW 3rd Floor) 5 Rx Bldg Sludge and Decant Pump Area 0.8 (S 2nd Floor) 6 Rx Bldg Neutron Monitor System Index 164 Area (TIP Room ist Floor) 7 Rx Bldg Neutron Monitor System Drive 1.8 Mech Area (SE 1st Floor) 8 Rx Bldg Control Rod Hydraulic Equipment 0.9 Area (S ist Floor) 9 Rx Bldg Control Rod Hydraulic Equipment 9 Area (N 1st Floor) 10 RX Bldg HPCI Pump Room (SW Quad) 25 11 Rx Bldg RHR Pump Room (SW Quad) 250 12 Rx Bldg RHR Pump Room (NW Quad) 250 13 Rx Bldg RCIC/CS Pump Room (NE Quad) 250 14 Rx Bldg CS Pump Room (SE Quad) 250 15 Turbine Bldg Turbine Front Standard 1 16 Turbine Bldg Mezz Control Corridor 0.2 17 Turbine Bldg Basement Control Corridor .05 18 Turbine Bldg Rx Feed Pump Area 1 19 Turbine Bldg Condensate Pump Area .12 20 Control Room Main Control Room .02 21 Grade Level Control Corridor .19 22 Radwaste Control Room .03 23 Radwaste Pump Room 5 24 Radwaste Basement Equipment Area 4 25 Radwaste Demineralizer Valve Room 1.2 26 Radwaste-Conveyor Aisle Operating Area 0.2 27- SPARE 28 Radwaste Lab Area .01 29 Centrifuge East 10 30 Centrifuge West 9 Panel 9-02 Personnel Airlock Area 903' 20 R/hr Panel 9-02 Ladder 903' to 2nd Level 20 R/hr OSH = Offscale High l
- _i______________._______ $ P 'W
- COOPER NUCLEAR STATION RADIATION MONITOR 8 1989 EVALUATED EXERCISE CLOCK TIME a 2145 8CENARIO TIME a 03/45
===========================================================
PANEL VBDG Rx Bldg Vent Eff (RMV-RM-40) 1.0E-3 uCi/see ERP Stack Normal Eff (RMP-RM-3A) 1.0E-3 uCi/sec _ ERP Stack High Range (RMP-RM-3 B) 0 uCi/see Turbine Bldg Vent Eff (RMV-RM-20A) 1.5E-3 uCi/sec Turbine Bldg High Range (RMV-RM-20B) 0 uCi/see RW/ARW Bldg Combined Eff (RMV-RM-30A) 8.2E-3 uCi/sec RW/ARW Bldg High Range (RMV-RM-30B) o uC1/see PANEL 9-10 Main Steam Rad Monitor Ch. A1, B1 15 mR/hr 15 mR/hr Ch. A2, B2 15 mR/hr 15 mR/hr SJAE Off Gas Log Rad Monitor Ch. A, B 1 mR/hr 1 mR/hr Rx Bldg Vent Ind/ Trip Unit Ch. A, B O.6 mR/hr 0.6 mR/hr
1989 EVALUATED EXERCISE Time = 2200 Message Number: 17 t= 04/00 COOPER NUCLEAR STATION-EMERGENCY PREPAREDNESS EXERCISE MESSAGE i Messaae for: Control Room Simulated Plant Conditions: See attached Plant Data Messaae: <
***THIS IS A DRILL ***
1989 EVALUATED EXERCISE Time = .2200 MESSAGE NUMBER: 17 t= 04/00 COOPER NUCLEAR STATION ) EMERGENCY PREPAREDNESS EXERCISE MESSAGE FOR CONTROLLER USE ONLY: Controller Informations ,p o Data sheet reflects operators plackeg SDC in service. Expected Actions: 1 o Monitor cooldown rate. l
i1989 EVALUATED EXERCISE Time a 2200 Nessage Number . 17_ . t= 04/00 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE PLANT DATA PANEL 9-3 PANEL 9-5 STATUS PRESS (psig) FLOW (gpm) REACTOR POWER 0% APRM
'RHR A- STBY 50 0 REACTOR LEVEL 53 " _EE_
RHR C STBY 50 REACTOR PRESSURE 50 (psig) RHR B SDC 240 7700 8 ELQH (10 lbs/hr) RHR D STBY 50 FEEDWATER A 0.0 CS A STBY 50 0 FEEDWATER B 0.0 CS B STBY 50 0 MAIN STEAM A 0.0 HPCI TRIPPED 50 0 MAIN STEAM B 0.0 Drywell Pressure 0.25 (psig) MAIN STEAM C 0.0 Torus Level 13,1 (feet) MAIN STEAM D 0.0 QEEE CLOSED CRD A FLOW 50 (gpm) MSIV O 8 CRD B FLOW 50 (gpm) SLC LEVEL 75 % PANEL 9-4 SLC PMP DISCH-PRESS A 0 SLC PMP DISCH PRESS B 0 STATUS PRESS (psig) FLOW (gpm) RCIC TRIPPED 50 0 RWCU A ISOL 0 0 MISCELLANEOUS PANELS l RWCU B ISOL 0 0 . RRP A 0 % SPD DIESEL GEN 1 STBY RRP B 0 % SPD DIESEL GEN 2 STBY SBGT A STBY SBGT B OPER j DRYWELL COOLING ISOL TORUS WATER TEMP 90 9F DRYWELL TEMP 122 9P
1989 EVALUATED EXERCISE Time = 2200 Message: 17 COOPER NUC MAR STATION t = __04/00 EMERGENCY PREPAREDNESS EXERCISE SPDS DATA Reactor Power (Avg % APRM) Reector Level (In.)
+150 120
+100 100
# +50 80 0
60 50 40 100 20 150 0 30 15 0 30 15 0 Reactor Pressure (psig) 1200 1000 800 600 400 200 0 30 -15 0 Dr pell Pressure (psig) Drywell Temperature (CF ) 300 75 ' 250 60 200 45 150 30 100 15 50 0 30 -15 0 0 30 15 0 Torus Level (in.) lorus Water f ernperature (OF )
+24 300 250
+12
- 200 0
150 100
-12 50
-24 0
-30 15 0 -30 15 0
4 COOPER NUCLEAR STATION RADIATION MONITORS 1989 EVALUATED EXERCISE CLOCK TIME a 2200 SCENARIO TIME = 04/00 STATION DESCRIPTION READING (mR/hr) 1 Rx Bldg Fuel Pool Area (SE 5th Floor) 154 2 Rx Bldg Fuel Pool Area (SE Sth Floor) 1.5 3 Rx Bldg New Fuel Area (SE 5th Floor) 0.3 4 Rx Bldg Rx Water Cleanup Demineralizer 113 Area (SW 3rd Floor) 5: Rx Bldg Sludge and Decant Pump Area 0.8 (S 2nd Floor) 6 RX Bldg Neutron Monitor System Index 164 Area (TIP Room ist Floor)
- 7. Rx Bldg Neutron Monitor System Drive 1.8 Mech Area (SE 1st Floor) 8 Rx Bldg Control Rod Hydraulic Equipment 0.9 Area (S ist Floor) 9 Rx Bldg Control Rod Hydraulic Equipment 9 Area (N 1st Floor) 10 Rx Bldg HPCI Pump Room (SW Quad) 25 11 Rx Bldg RHR Pump Room (SW Quad) 250 12 Rx Bldg RHR Pump Room (NW Quad) 250 13 Rx Bldg RCIC/CS Pump Room (NE Quad) 250 14 Rx Bldg CS Pump Room (SE Quad) 250 15 Turbine Bldg Turbine Front-Standard 1 16 Turbine Bldg Mezz Control Corridor 0.2 17 Turbine Bldg Basement Control Corridor ,05 18 Turbine Bldg Rx Feed Pump Area 1 19 Turbine Bldg Condensate Pump Area .12 20 Control Room Main Control Room .02 21 Grade Level Control Corridor .19 22 Radwaste Control Room .03 23 Radwaste Pump Room 5 24 Radwaste Basement Equipment Area 4 25 Radwaste Demineralizer Valve Room 1.2 26 Radwaste Conveyor Aisle Operating Area 0.2 27 SPARE 28 Radwaste Lab Area .01 29 Centrifuge East 10 30 Centrifuge West 9 Panel 9-02 Personnel Airlock Area 903' 20 R/hr Panel 9-02 Ladder 903' to 2nd Level 20 R/hr OSH = Offscale High
COOPER NUCLEAR STATION RADIATION NONITORS 1989 EVALUATED EEERCISE CLOCE TIME a 2200 SCENARIO TIKE a 04/00
=======================================================================
PANEL VBDG i Rx Bldg Vent Eff (RMV-RM-40) 1.0E-3 uCi/see ERP Stack Normal Eff (RMP-RM-3A) 1.0E-3 uCi/sec ERP Stack High Range (RMP-RM-3B) o uCi/sec Turbine Bldg Vent Eff (RMV-RM-20A) 1.5E-3 uCi/sec Turbine Bldg High Range (RMV-RM-20B) 0 uCi/see RW/ARW Bldg Combined Ef f (RMV-RM-30A) 2.0E-3 uCi/sec RW/ARW Bldg High Range (RMV-RM-30B) 0 uC1/sec PANEL 9-10 Main Steam Rad Monitor Ch. A1, B1 15 mR/hr 15 mR/hr Ch. A2, B2 15 mR/hr 15 mR/hr SJAE Off Gas Log Rad Monitor Ch. A, B 1 mR/hr 1 mR/hr, Rx Bldg Vent Ind/ Trip Unit Ch. A, D 0.6 mR/hr 0.6 mR/hr i e
1989 EVALUATED EXERCISE Time = 2215 Message Number: 18 t= 04/15 COOPER NUCTPAR STATION DERGENCY PREPAREDNESS EXERCISE MESSAGE Messaae for: Control Room Simulated Plant Conditions: See attached Plant Data Mess _Agg:
***THIS IS A DRILL ***
I i i \ l l 1 i l L l l 1 l
l 1 1989 EVAIDATED EXERCISE Time = 2215 I l MESSAGE NUMBER: 18 t= 04/15 I COOPER NUCLEAR STATION l EMERGENCY PREPAREDNESS EXERCISE MESSAGE FOR CONTROr.T FR USE ONLY: Controller Information: Expected Actions: ' 1 l i l 1 l 1
1989 EVALUATED EXERCISE Time
- _2215 s
' Message Numbert . 18 t= 04/15 COOPER NUCLEAR STATION ' EMERGENCY PREPAREDNESS EXERCISE PLANT DATA PANEL 9-3 PANEL 9-5 STATUS- PRESS (psig) ELQW(gpm) REACTOR POWER 0% APRM RHR A STBY 50 0 REACTOR LEVEL 53 " NR RHR C STBY 50 REACTOR PRESSURE 20 (psig) RHR B SDC 240 7700 FLOW (10' lbs/hr) RHR D STBY 50 FEEDWATER A 0.0 CS A STBY 50 0 FEEDWATER B 0.0 CS B STBY 50 0 MAIN STEAM A 0.0 HPCI TRIPPED 50 0 MAIN STEAM B O.0 l Drywell Pressure 0.25 (psig) MAIN STEAM C 0.0 l Torus Level , 13.1 (feet) MAIN STEAM D 0.0 OPEN CLOSED CRD A FLOW 50 (gpm) MSIV O 8 CRD B FLOW 50 (gpm) SLC LEVEL 75 % PANEL 9-4 SLC PMP DISCH PRESS A 0 SLC PHP DISCH PRESS B 0 STATUS PRESS (psig) FLOW (gpm) RCIC- TRIPPED 50 0 RWCU A ISOL 0 0 MISCELLANEOUS PANELS RWCU B ISOL 0 0 RRP A 0 % SPD DIESEL GEN 1 STBY RRP B 0 % SPD DIESEL GEN 2 STBY SBGT A STBY SBGT B OPER DRYWELL COOLING ISOL TORUS WATER TEMP 87 9P DRYWELL TEMP 122 T
- . - - . . . -- . . . . - = . - . . . .
)
i l l 1989 EVALUATED EXERCISE Time = 2215 Message: 18 COOPER NUCLEAR STATION t= 04/15 EMERGENCY PREPAREDNESS EXERCISE SPDS DATA Reactor Power ( Avg % APitr ' Reactor Level (in.)
+150 120
+100 100 _
r +50 l g . 0 60 50 40 100 20 150 0 30 15 0 30 15 0 Reactor Pressure (psig) 1200 1000 800 600 400 200 3; 15 0 e Drywell Pressure (psig) Drywell Tenperature ('F) 300 75 250 60 200 45 150 30 100 15 50 0 30 15 0 30 -15 0 Torus Level (in.) Torus Water Temperature (OF )
+24 300 5
250
+12 200 0 150 l
100 l 12 c 50 l_ -24 0 1 -30 -15 0 30 15 0
l l COOPER NUCLEAR STATION RADIATION MONITOR 8 1989 EVALUATED EEERCISE CLOCK TIME a 2215 SCENARIO TIME = 04/15 STATION DESCRIPTION READING (mR/hr) 1 2 Rx Bldg Fuel Pool Area (SE Sth Floor) 154 3 Rx Bldg Fuel Pool Area (SE Sth Floor) 1.5 Rx Bldg New Fuel Area (SE 5th Floor) 0.3 4 Rx Bldg Rx Water Cleanup Demineralizar 113 5 Area (SW 3rd Floor) Rx Bldg Sludge.and Decant Pump Area 0.8 (S 2nd Floor) 6 Rx Bldg Neutron Monitor System Index 164 7 Area (TIP Room ist Floor) Rx Bldg Neutron Monitor System Drive 1.8 8 Mech Area (SE 1st Floor) Rx Bldg Control Rod Hydraulic Equipment 0.9 9 Area (S 1st Floor) Rx Bldg Control Rod Hydraulic Equipment 9 10
. Area-(N 1st Floor)
Rx Bldg HPCI Pump Room (SW Quad) 25 11 Rx Bldg RHR Pump Room (SW Quad) 250 12 Rx Bldg RHR Pump Room (NW Quad) 250 13 Rx Bldg RCIC/CS Pump Room (NE Quad) 250 14 Rx Bldg CS Pump Room (SE Quad) 250 15 Turbine Bldg Turbine Front Standard 1 16 Turbine Bldg Mezz Control Corridor 0.2
-17 Turbine Bldg Basement Control Corridor .05 18 Turbine Bldg Rx Feed Pump Area 1 19 Turbine Bldg Condensate Pump Area .12 20 Control Room Main Control Room .02 21 Grade Level Control Corridor .19 22 Radwaste Control Room .03 23 Radwaste Pump Room 5 24 Radwaste Basement Equipment Area 4 25 Radwaste Demineralizer Valve Room 1.2 26 Radwaste Conveyor Aisle Operating Area 0.2 27 SPARE 28 Radwaste Lab Area .01 29 Centrifuge East 10 30 Centrifuge West 9 Panel 9-02 Personnel Airlock Area 903' 20 R/hr Panel 9-02 Ladder 903' to 2nd Level 20 R/hr OSH = Offscale High
1 ' COOPER NUCLEAR STATION RADIATION MONITORS 1989 EVALUATED EXERCISE CLOCK TIME a 2215 8CENARIO TIME a 04/15
.== ...................................................................
PANEL VBDG Rx Bldg Vent Eff (RMV-RM-40) 1.0E-3 uCi/sec ' ERP Stack Normal Eff (RMP-RM-3A) 1.0E-3 uCi/sec ERP Stack High Range (RMP-RM-3B) 0 uci/see Turbine Bldg Vent Eff (RMV-RM-20A) 1.5E-3 uCi/sec Turbine Bldg High Range (RMV-RM-20B) o uCi/see RW/ARW Bldg Combined Eff (RMV-RM-30A) 2.OE-3 uCi/sec RW/ARW Bldg High Range (RMV-RM-30B) 0 uci/sec PANEL 9-10 Main Steam Rad Monitor Ch. A1, B1 15 mR/hr 15 mR/hr Ch. A2, B2 15 mR/hr 15 mR/hr SJAE Off Gas Log Rad Monitor Ch. A, B 1 mR/hr 1 mR/hr Rx Bldg Vent Ind/ Trip Unit Ch. A, B 0.6 mR/hr 0.6 mR/hr i
1989 EVALUATED EXERCISE Time = 2230 Message Number: __Jg t= 04/30 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE Messace fort Control Room simulated Plant Conditions: See attached Plant Data Message
***THIS IS A DRILL ***
Indications in the Control Room include: Reactor coolant temperature = 195F l m -
I i '1989 EVALUATED EXERCISE Time = 2230 MESSAGE NUMBER: _11_ t= 04/30 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGB FOR CONTROLLER USE ONLY: Controller Informations o The plume is dispersed out of the 10 mile EPZ. The reactor is placed in a stable, cold shutdown condition. Expected Actionst o Commence downgrade / termination discussions.
[' . 1989-EVALUATED. EXERCISE Time a _ 2 2 30 Message Numbert _11_ t= 04/30 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCI8E PLANT DATA PANEL 9-3 PANEL 9-5 STATUS PRESS (psig) FLOW (gpm) REACTOR POWER 0% APRM RHR A STBY 50 0 REACTOR LEVEL 53 " _EE_ RHR C STBY 50 REACTOR PRESSURE o (psig) RHR B SDC 240 7700 6 ELQH (10 lbs/hr) RHR D STBY 50 FEEDWATER A 0.0 CS A STBY 50 __ 0 FEEDWATER B 0.0 CS B STBY 50 0 MAIN STEAM A 0.0 HPCI TRIPPED 50 0 MAIN STEAM B 0.0 Drywell Pressure 0.25 (psig) MAIN STEAM C 0.0 Torus Level 13.1 (feet) MAIN STEAM D 0.0 OPEN CLOSED CRD A FLOW 50 (gpm) MSIV O 8 CRD B FLOW 50 (gpm) SLC LEVEL 75 % PANEL 9-4 SLC PMP DISCH PRESS A 0 I SLC PMP DISCH PRESS B 0 STATUS PRESS (psig) FLOW (gpm) ! RCIC TRIPPED 50 0 ) RWCU A __ISOL 0 0 MISCELLANEOUS PANELS RWCU B ISOL 0 0 RRP A 0 % SPD DIESEL GEN 1 STBY RRP B 0 % SPD DIESEL GEN 2 __ETJ1Y__ SBGT A STBY SBGT B OPER DRYWELL COOLING ISOL TORUS WATER TEMP 85 T DRYWELL TEMP 122 T
1 1989 EVALUATED EXERCISE Time == 2230 Mossage: 19 : COOPER NUCLEAR STATION t= - 04/30 EMERGENCY PREPAREDNESS EXERCISE SPDS DATA I Reactor Power ( Avg 1 APRM) Reactor Level (in.) )
+150 120 j
+100 '
100
+50 I 80 0
60 50 40 100 20 150 0 30 15 0 30 15 0 Reactor Pressure (psig) 1200 1000 800 600 400 200 0 30 15 0 DryweLL Pressure (psig) Drywell Temperature (OF ) 300 75 250 60 200 45 150 30 100 15 50 0 0 30 15 0 30 15 0 Torus Level (In.) forus Water Tenperature (OF )
+24 300 250
+12 200 0 150 100
-12 50
-24 0 30 15 0 -30 -15 0
. . ~ . , . . ..
. . -~ .- - - -- - . - _ . - -.-~ - .- k COOPER NUCLEAR STATION RADIATION NONITORS 1989 EVALUATED EXERCISE CLOCK TIME a 2230 SCENARIO TIME = 04/30
..m................................................................ .
STATION DESCRIPTION READING (mR/hr) 1 Rx Bldg Fuel Pool Area (SE Sth Floor) 154 2 Rx Bldg Fuel Pool Area. (SE 5th Floor) 1.5 3 Rx Bldg New Fuel Area (SE Sth Floor) 0.3 4 Rx Bldg Rx Water Cleanup Demineralizer 113 Area (SW 3rd Floor) 5 Rx Bldg Sludge and Decant Pump Area 0.8 (S 2nd Floor) 6 Rx Bldg Neutron Monitor System Index 164 Area (TIP Room ist Floor) 7 Rx Bldg Neutron Monitor System Drive 1.8 Mech Area (SE 1st Floor) 8- Rx Bldg Control Rod Hydraulic Equipment 0.9 Area (S ist Floor) 9 Rx Bldg' Control Rod Hydraulic Equipment 9 Area (N-1st Floor) 10 Rx Bldg HPCI Pump Room (SW Quad) 25 11 Rx Bldg RHR Pump Room (SW Quad) 250 12 Rx Bldg RHR Punp Room (NW Quad) 2 5,p 13 Rx Bldg RCIC/CS Pump Room (NE Quad) 250 14 Rx Bldg CS Pump Room (SE Quad) 250 15 Turbine Bldg Turbine Front Standard 1 16 Turbine Bldg Mezz Control Corridor 0.2 17 Turbine Bldg Basement Control Corridor .05 18 Turbine Bldg Rx' Feed Pump Area 1 19 Turbine Bldg Condensate Pump Area .12
'20 Control Room Main Control Room .02 21 Grade Level Control Corridor .19 -22 Radwaste Control Room .03 23 Radwaste Pump Room 5 24 Radwaste Basement Equipment Area 4 25 Radwaste Demineralizer Valve Room 1.2 26 Radwaste Conveyor Aisle Operating Area 0.2 27 SPARE 28 Radwaste Lab Area .01 29 Centrifuge East 10 30- Centrifuge West 9 Panel 9-02 Personnel Airlock Area 903' 20 R/hr Panel 9-02 Ladder 903' to 2nd Level 20 R/hr OSH = Offscale High ;
I l
COOPER NUCLEAR STATION RADIATION NONITORS 1989 EVALUATED EEERCISE CLOCK TIME a 2230 SCENARIO TIME a 04/30 === ..................--............................................... PANEL VBDG Rx Bldg Vent Eff (RMV-RM-40) 1.0E-3 uCi/sec ERP Stack Normal Eff (RMP-RM-3A) 1.0E-3 uCi/sec ERP Stack High Range (RMP-RM-3B) 0 uCi/see Turbine Bldg Vent Eff (RMV-RM-20A) 1.5E-3 uCi/see Turbine Bldg High Range (RMV-RM-20B) 0 uci/sec RW/ARW Bldg Combined Eff (RMV-RM-30A) 2.OE-3 uCi/sec RW/ARW Bldg High Range (RMV-RM-3 0B) 0 uci/sec PANEL 9-10 Main Steam Rad Monitor Ch. A1, B1 15 mR/hr 15 mR/hr Ch. A2, B2 15 mR/hr 15 mR/hr SJAE Off Gas Log Rad Monitor Ch. A, B 1 mR/hr 1 mR/hr Rx Bldg Vent Ind/ Trip Unit Ch. A, B 0.6 mR/hr 0.6 mR/hr
1989 EVAIDATED EXERCISE Time = 2245 Message Number: 20 t= 04/45 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE Messaae for: Control Room Simulated Plant Conditions: See attached Plant Data I Message: 1
***THIS IS A DRILL ***
1 l l l 1 l l L i l l l 1 l
1989 EVALUATED EXERCISE Time = 2245 MESSAGE NUMBER: 20 t= 04/45 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE FOR CONTROTTER USE ONLY: Controller Information: Expected Actions:
1989 EVALUATED EXERCI8E Time a _2245 Message Numbert- _la_, ta 04/45 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE PLANT DATA PANEL 9-1 PANEL 9-5 STATUS PRESS (psig) FLOW (gpm) REACTOR POWER 0% APRM 1U01 A STBY 50 0 REACTOR LEVEL 53 " NR RHR C- STBY 50 REACTOR PRESSURE O (psig) RHR B SDC 240 7700 6 W ELQW (10 lbs/hr) RHR D STBY 50 FEEDWATER A 0.0 CS A STBY 50 0 FEEDWATER B 0.0 CS B STBY 50 0 MAIN STEAM A 0.0 HPCI TRIPPED 50 0 MAIN STEAM B 0.0 Drywell Pressure 0.25 (psig) MAIN STEAM C 0.0 Torus Level 13.1 (feet) MAIN STEAM D 0.0 OPEN CLOSED CRD A FLOW 50 (gpm) MSIV O 8 CRD B FLOW 50 (gpm) SLC LEVEL 75 % PANEL 9-4 SLC PMP DISCH PRESS A 0 SLC PMP DISCH PRESS B 0 STATUS PRESS (psig) FLOW (gpm) RCIC TRIPPED 50 0 RWCU A ISOL 0 0 MISCELLANEOUS PANELS RWCU B ISOL 0 0 RRP A 0 % SPD DIESEL GEN 1 STBY RRP B 0 % SPD DIESEL GEN 2 STBY SBGT A STBY SBGT B OPER DRYWELL COOLING ISOL TORUS WATER TEMP 84 9F DRYWELL TEMP 122 9P i
~
-1989 EVALUATED EXERCISE Time = 2245 Message: 20 COOPER NUCfRAR STATION t= 04/45 i i FMERGENCY PREPAREDNESS EXERCISE SPDS DATA ! Reactor Power (Avg 1 APRM) Reactor Level (In.)
+150 120
+100 100
+50 80 O
60 50 40 100 ! 20 150 0 30 15 0 30 ,15 0 i Reactor Pressure (psig) 1200 ; 1000 800 600 400 200 I 0 i 30 -15 0 ! Drywell Pressure (psig) Drywell Temperature (OF ) 300 75 250 60 l 200 45 150 30 100 15 50 0 30 13 0 30 13 o Torus Level (in.) Torus Water Temperature (OF )
+24 300 250
+12 200 0 150 100 12 50
-24 0 l 30 15 0 30 15 0
COOPER NUCLEAR STATION RADIATION NONITOR8 - 1989 EVALUATED EXERCISE CLOCK TIME a 2245 \ SCENARIO TIME = 04/45 maammmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmen STATION DESCRIPTION READING (mR/hr) . 1 Rx Bldg Fuel Pool Area (SE Sth Floor) 154 7 Rx Bldg Fuel Pool Area (SE 5th Floor) ____ 1.5 3 Rx Bldg Now Fuel Area (SE Sth Floor) . ~ 0.3 4 Rx Bidg Rx Water Cleanup Domineralizer 113 Area (SW 3rd Floor) ; 5 Rx Bldg Sludge and Decant Pump Area 0.8 (S 2nd Flocr) i 6 Rx Bldg Neutron Monitor System Index 164 1 Area (T'4P Rocn lat Flocr) ! 7 8x Bldg Neutron Monitor System Drive 1.8 a Mech Arsa (SE ist Floor) 8 Rx Bldg Control Rod Hydraulic Equipment ___ 0.9 _ _ _ _ i Area (S ist Floor) - 9 Rx Bldg Control Rod Hydraulic Equipment 9 .,
}
Area (N 1s'; Floor) 10 Rx Bldg MPCI Pump Room (SW Quad) 25 11 Rx Bldg RHR Pump Room (SW Quad) 250 12 Rx Bldg RHR Pump Room (NW Quad) 250 13 Rx Bldg RCIC/CS Pump Room (NE Quad) 250 Rx Bldg CS Pump Room (SE Quad) 14 250 - 15 Turbine Bldg Turbine Front Standard i 16 Turbine Bldg Metz Control Corridor 0.2 ,, 17 Turbine Bldg Basement Control Corridor .05 18 Turbine Bldg Rx Feed Pump Area 1 19 Turbine Bldg Condensate Pump Area .12 20 Control Room Main Control Room .02 21 Grade Level Control Corridor .19 22 Radwaste Control Room .03 23 Radwaste Pump Room 5 24 P'i dwaste Basement Equipment Area 4 25 hauwaste Domineralizer Valve Room 1.2 26 Radwaste Conveyor Aisle Operating Area 0.2 27 SPARE 28 Radwaste Lab Area .01 29 Centrifuge East 10 ; 30 Centrifuge West 9 Panel 9-02 . Personnel Airlock Area 903' 20 R/hr Panel 9-02 Ladder 903' to 2nd Level 20 R/hr OSH = Offscale High
i COOPER WUCLEAR STATION RADIATION MONITORS 1949 EVALUATED EEERCISE CLOCR TIME a 2245 SCENARIO TIME a 04/45 PANEL VBDG P.x Bldg Vent Eff (RMV-RM-40) 1.or-3 uci/see ERP Stack Normal Eff (RMP-RM-3A) _1.or-3.uci/see , ERP Stack High Range (RMP-RM-35) o uci/see j Turbine Bldg Vent Eff (RMV-RM-20A) _1.5E-3 uci/see Turbine Bldg High Rangs (RMV-RM-20B) _0 uci/ge RW/ARW Bldg Combined Eff (RMV-RM-30A) ,_Lpf-2 uci/ag.g RW/ARW Bldg High Range (RMV-RM-30B) ,R _, a ti/see _ _ _ , , P PANEL 9-1,2 Main StearA Rad Monitor Ph. A3, B1 15 mR/hr 15 MB4hr Ch. A2, B2 15 mR/_hr_ 15 mP>hr SJAE off Gaz Log Pad Monitor Ch. A, B 1 mR/hr LaRlAr Rx Bldg Vent Ind/ Trip Unit Ch. A, B _0. 6 mP/Ar._QdAR/hr_
1989 EVALUATED EXERCISE Time = ~2300 l i Message Number: 21X t = '05/00 COOPER NUCLEAR STATION EMERGENCY PREPAREDNES8 EXERCI8E MES8 AGE i Massaae fort Recovery Director simulated Plant conditions: MasAnat:
*** TRIS I8 A DRILLe**
The Exerciso may be terminated at your discretion.
t i 1989 EVALUATED EXERCISE Time = 2300 MESSAGE NUMBER: 21X t= 05/00 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE FOR CONTROLLER USE ONLh ! Controller Informationt l o Deliver when all drill objectives have Deen demonstrated. ! o Ensure that "closecut" PA renounceuent is made. Expected Actiontar o Terminate the drill. Notify all Emergency Response Facilities. Make PA announcement that the drill is terminated. I i l l
l SUPPLEMENTAL SCENARIO NO. 1 RPCI RUPTURE / ISOLATION VALVE FAILURES TIME: 1815 to 2130 Location! HPCI ROOM--Rx Bldg 859' elevation (initially) MCC-R--Rx Bldg. 903' elevation (breaker for HPCI MO-15) SE diagonal--Rx. Bldg 859' elevation (breaker for MO-16) Angle Valve Room--Rx. Bldg 903' elevation (HPCI MO-16) A. Initial Fotification control Room operators are alerted to the HPCI pipe rupture , by annunciators and indications on Message No. 2. Additionally, the Station Operator will be provided concurrent information in Message No, SSI.1. E. Eostulated Event It is postulated that HPCI experiences a rupture at the flanged entnection between the HPCI turbine step valve and centrol valve. The stop valve cutomatically closes, which essentially isolates the rupture. The HPCI outboard steam supply isolation valve is mechanically bound, so when it receives its automatic isolation, its breaker trips on overload. The HPCI inboard steam supply isolation valve has a faulty closing coil at:d relay, which prevents the valve from stroking fully closed. This failure to isolate warrants an ALERT declaration. Please see the attached, annotated simplified system diagram. C. Restoration Guidelines The HPCI inboard steam supply isolation valve is closed at 2130 by OSC teams. This rastores containment integrity. This valve cannot be closed before 7115 as it will isolate the release path. l
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- l 1989 EVALUATED EXERCISE Time z _1815 Message Number 881.1 t= 00/15 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE Messaae fort Station Operater Observing RPCI Operability Test Riggsted Plant C,gnditiorigt P
Massace: T
***TEIS IS A DRILL ***
As the Control Room operator s'terted HPCI, you saw a lot of steam leaking from the flange between the HPCI turbino stop valve and control valve. You got scared and left the room as fast as you
- could. A few seconds after you got out of the room, you heard a -
loud " pop" and rustaing steam,- followed by the sounds of the HPCI turbitte tripping and numerous valves repositioning. There is D2 , steam coming out of the HPCI Room door now, although some steam came out right after the " pop" sound. P l l l I
1989 EVALUATED EXERCISE Time m *1830 Message Numbert 831.2X t u *00/30 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE Message fort Statica Operator /OSC Team Investigating Breaker for HPCI Inboard containment Isolation Valva (MO-15) Simulated Plant Cp h {gng: Messaget
*** TRIS IS A DRILL ***
Station Operator--Breaker appears normal, there is no apparent , cause for the valve not closing. ; of>C Team--Af ter allowing the team to troubleshoot, inforts them whe:t they would discover (if they would) *. hat the breaker has a faulty closing coil. Heat from the coil has caused swelling and varnish leaks, rendering the relay inoperable. The relay requires .- replacement. I
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t i 1989 EVALUATED EXERCISE Time z '1830 i Message Number: 881.3X t = ~00/30 COOPER NUCLEAR STATION EMERGENCY PREPAREDNES8 EXERCISE MESSAGE Message fort station operator /Osc Tema Investigating areaker for , EPCI outboard Containment Isolation Valve (MO-16) nr Surveying EPCI Room damage
#_laulatsd Plant Conditionst Messace
*** TRIS IS A DRILL ***
Thz breaker for MO-16 is tripped, apparently on thermal overload. There is a rupture at the flange between the HPCI turbine control valve and stop valve. P
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1989 EVALUATED EXERCISE Time = ~1830 , Message Numbert sei.4X t = '00/30 ! i i COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS.. EXERCISE MESSAGE Messaae fort station operator /osc Team Investigating MPCI outboard ! Containment Isolation Valve (MO-16) simula,ted Plant Conditionst , Messaqat
***THIS IS A DRILL ***
The valve can not ba turned using the manual oper:4 tor, no matter how hard you try. ' t
=
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- i 1989 EVALUATED EXERCISE Time z ~2130 [
Message Numbert asi.5 t: o3/30
. s.
COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE Message fort OSC Team Repairing Breaker for RPCI Inboard Containment Isolation valve (No-15) Simulated Plant Conditionst [ Hessarat
*** TRIS IS A DRILLe**
You have installed a now cicsing coil and relay. Its functioning appears to be satirfactory. P O l
SUPPLEMENTAL SCENARIO NO. 2 DUAL RECIRCULATXON PUMPS TRIP WITHOUT COASTDOWN Tl m 1930 , Location: Aux. Relay Room (Control Building 903' elevation) A. Initial Notification Control Room operators are alerted to the dual recirculation pumps trip w/o coastdown by control Room annunciators and indications on Message No. 7. B. 228.t.u)ated Event It is postulated that I&C technicians were troubleshooting the ARI-RPT indicating light in PNL C22-P001 at the start of the , scenario. At the ALZRT declaration, they vacated their work area without properly securing all of their jumpers and lifted leads. At 1930, a jumper at point A6 in this panel has the alligator clip on one end become detached. It touches, sequentially, points A8 and A9. This results in the trip coil to be energized for each Recirculation pump MG net Field Breakeri and a consequent, rapid, sequential trip of both - Recirculation pumps without coastdown. See attached, annotated diagram. C .' Restoration Guidelines N/A - Recirculation can be restored at anytime after 1933. Procedural constraints prevent operators from restoring recirculation pumps between 1930 and 1933.
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6 1989 EVALUATED EXERCISE Time m ~2130 Message Number 882.1X ta '03/30 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS EXERCISE MESSAGE l Message fort 08C Team Investigating Dual Recirculation Pump Trip simulated Plant Conditions: Messaget
*** TRIS IS A DRILL ***
In Panel C22-P001, you find a jumper dangling from point A6. By looking at the prints, you conclude that one end could have come loose and made contact with points A8 and A9, and that this would result in a dual recirculation pump trip. w
k SUPPLEMENTAL SCENARIO No. 3 LOSS OF SRV ELECTRICAL FUNCTION TIMEt, 1933 to 2115 Location: Aux. Relay Room (Control Building 903' elevation) A. Initial Notificatl72 Control Room operators are alerted to the loss of SRV electrical function by Control Room annunciators and indications on Message No. 7.1X. B. Postulated Event It is postulated that SRV 71F has a ground at the solenoid. When the solenoid is energized, the ground condition causes the 30 Amp fuses from the 125VDC power to supply to blow. The 10 Amp fuses protecting SRV 71F do not blow since the fuses were snadvertantly replaced with 40 Amp fuses. When the power supply for this set of SRVs automatically transfers to the other power supply (which also provides normal power supply to the other 50% of the SRVs), that power supply becomes faulted, and its 30 Amp fuses blow. This results in the loss of all electrical functioning (ADS, LLS, and manual) of the SRVs due to loss of power. SFVs will still function in the safety (mechanical) aode. See attached, annotated diagram. - C. Restoration Guidelines To restore SRV operability the 40 Amp fuses for SRV 71F must be pulled or replaced with 10 Amp fuses. Additionally, the blown 30 Amp fuses for at least one power supply must be replaced. The OSC controller must inform the CR controllers regarding which SRVs are returned to service, based on the repairs actually made by the OSC team. SRV operability must be restored between 2110 and 2115 so that can operators can emergency depressurize and terminate the release.
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l 1989 EVALUATED EXERCISE Time = ~1945 Message Number: 884.1X ta ~01/45 ! COOPER NUCLEAR. STATION I EMERGENCY PREPAREDNESS. EXERCISE MESSAGE Messace fort Station Operator /OSC Team investigating AOG MO-920/1 l Simulated Plant. Conditions: Messages
***THIS IS A DRILL ***
The motor operator for MO-920 is working but the valve is not moving. Looks like the gearing may be stripped. If attempts are made to manually, close the valve, the clutch for the motor , operator will not disengage. l 1 The actor operator has no power. If attempts are made to manually close the valve, no matter hew much force is applied, no stem i movement la observed. l I 1 __.x_______. -. - .-.
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1989 EVALUATED EXERCISE Time m 1945 Message Number: ss4.2X t = '01/45 , COOPER NUCLEAR.8TATION EMERGENCY PREPAREDNESS EXERCISE MEp5 AGE Hassaae fort station operator /osc Maintenance team Investigating Breakers for Aoo Mo-920/1 Simulated Plant Conditions: Messaue
** TRIS IS A DRILL ***
4737 The breaker for MO-93 appears fine. The breaker for MO-921 is tripped, apparently on thermal overload. It can be reset, but trips anytime an attempt is made to electrically close the valve. 8
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i l l 1 1989 EVALUATED EXERCISE Time a '1945_
. Message Numbert 884.3X ta *01/45 COOPER NUCLEAR STATION .
i 1 Message fort Station Operator /OSC Maintenance team sent to AOG l Control Room to remotely close AOO air operated valves , l Simulated Plant conditionst ' 1 Messaget
*** TRIS IS A DRILL ***
The door to the AOG Control Room is locked. When you put the key I in, it broke off without unlocking the door. . B B 4
- - _ . . . . . - _ _ _ _ , , . - - . ~
a I 1:- b" SUPPLEMENTAL SCENARIO NO. 5 La' RCIC TURDINE TRIP TIME: 1945 to End of Scenario Japption: RCIC Room A. Initial Notification Control Room operators are alerted to the RCIC overspeed trip by Control Room annunciators and indications on Message No. 8. B. Postulated Event It is postulated that RCIC experiences a spurious overspeed , trip. When this occurs, the overspeed trip mechanism " flies apart". C. Restoration Guidelines NONE--Repair teams cannot reassemble the overspeed trip mechanism daring the time frame of the scenario. 9
1989 EVALUATED EXERCISE Time = ~2000 Message Number 885.1X t = *02/00 COOPER NUCLEAR STATION EMERGENCY PREPAREDNESS. EXERCISE.NESSAGE Message fort Station Operator /Osc Maj.ntenance team sent to RCIC simulated Plant Conditions: Messages
*** TRIS Is A DRILL ***
When you attempt to reset the overspeed trip device, you note that it has " sprung" apart and that pieces are all of the floor. i l l 1 l l l l
h- > P 1 i l l, N SECTION 9.0 RADIOCHEMISTRY SAMPLE AND RADIATION DATA 1 l. l l l l l
SECTION 9: Radiochemistry Samole and InDlant Radiation Data 9.0 Introduction , 9.1 Radiochemistry Sample Data Table 9.1.1: Reactor Coolant Sample Data Table 9.1.2: Drywell Atmosphere Sample Data Table 9.1.3: Torus Liquid Sample Data Table 9.1.4: Torus Atmosphere Sample Data 9.2 Area Radiation Data Table 9.2.1: Area Radiation Monitor Trend Data Figure / Table 9.2.2: Reactor Building (El. 1001') , Figure / Table 9.2.3: Reactor Building (El. 976') Figure / Table 9.2.4: Reactor Building (El. 958') Figure / Table 9.2.5: Reactor Building (El. 931') Figure / Table 9.2.6: Reactor Building (El. 903') Figure / Table 9.2.7: HPCI Pump Room Figure / Table 9.2.8: Reactor Building (El. 8598-882') Figure / Table 9.2.9: Turbine Building (El. 932') Figure / Table 9.2.10: Turbine Building (El. 903'-909') Figure / Table 9.2.11: Turbine Building (El. 862') Figure / Table 9.2.12: Control Corridor (El. 903') Figure / Table 9.2.13: Augmented Radwaste Building (El. 877') Figure / Table 9.2.14: Augmented Radwaste Building (El. 903') Figure / Table 9.2.15: Outside Areas i
*^
Lv--.
P t SECTION
9.0 INTRODUCTION
l
9.0 INTRODUCTION
This section provides the information necessary for participants to evaluate the extent of core / clad damage and the effect of the ' release upon the in-plant environment. Section 9 furnishes scenario controllers the specific data ' necessary for providing participants the information that simulates the radiochemical and environmental conditions of the postulated event. Section 9.1 includes radiochemistry sample tables with the information used to. assess the extent of the core / clad damage. Section 9.2 contains area radiation data along with gross airborne activities and contamination levels fcund throughout the plant.
t
\
SECTION 9.1 RADIOCHEMISTRY SAMPLE DATA 1 1 .' 1
TARI:9.1.la
!! ACTOR C00LAlit hCi/cc)
IS0f0ft 1800 1930 1945 2000 2015 2030 20(5 2l00 2115 Er-85s f.12803 2.81t+00 2.59t+00 2.40t+00 2.08t+00 1.81t+00 1.46t-01 3.5(I01 6.851-02 tr-85 1.65t03 6.52101 6.18t01 5.88101 5.(!!-01 4,85801 2.08t01 1.031-01 2.068-02 tr-87 7.2(I03 2.86t+00 2.38t+00 1.99tt00 1.58t+00 1.25t+00 4.661-01 2,018-01 3.51102 tr88 1.53102 6.0(I+00 5.44t+00 (.91t+00 4,18t+00 3.55t+00 1. 43 t+ 00 6.67101 1.25101 te 133 3.09801 1,22t+02 1.17!402 1.12t+0! 1.Oll*02 9.12I601 3.90!+01 1.93t+0! .3,85t+00 Ie 135 6.39102 2.53t+01 2.29t+01 2.lfit0! 1.92t+01 1.T!!+01 1,16t*00 3.47t+00 6.85t01 TOTALI.G. 4.02801 1.59t+s2 1.51t+02 1.44t+02 1.29t+02 1.15t*02 4.91It0! 2.41t+01 (19t+00 .1131 1.42t-02 2.25I402 2,15t+02 2.06t+02 1.87t+02 1.69tt02 7.21t+0! 6.57tt01 6.57t+01 1132 1.81t03 2.86t+0! 2,54t+0! 2.26t+01 1.90t+0! 1.60l+01 6.32t+00 5.35tt00 4.96t+00 1133 9.76t03 1.5(It02 1,46t+02 1.39t+02 1.25t+02 1.13t+02 4.fft+01 4,31t+01 4.271401 1134 2.21t03 3.(91+01 2.74I401 2.16t+01 1.31t+01 1.!!!+0! 4.17t+00 3.135t00 2.56t+00 1135 5.18103 8.19t+0! 7.65t+01 f.15t*01 6.30t+01 5.56t+0! 2.32t+01 2.058601 2.00t+01 TOTAL 10D!ll 3.32802 5.25t402 (90t+02 4.61t*02 4.09t+02 3.66tt02 1.53t+02 1.38t+02 1.36t+02 Cs 134 0.00t+00 9.51801 9.08101 9.10E01 9.08801 9.10t01 9.09t-01 9.09801 9.10I01 Cs-137 0,008400 5.89101 5.628-01 5.631-01 5.63t-01 5.628-01 5.63t01 5.62t01 5.63101 Cs 138 0.00t+00 2.89802 2.00t02 1.(5t02 1.05802 7.60E03 5.51t03 3.99t03 2.89103 Alt.HtfALS 0.00t+00 1.57t+00 1.(9t+00 1.491400 1,48 t+00 1.48tt00 1.48t*00 1,48t+00 1.47t+00 fe 132 0.00t+00 0.00t+00 0.00t100 0.00It00 0.00t400 0.00t*00 0.00t+00 0,00t+00 0.00t+00 St-91 d.00l+00 0.00t+00 0.00!f00 0.00t+00 0.00t+00 0.00t*00 0.00t+00 0.00tt00 0.00t+00 St-92 0.00t+00 0.00t+00 0.00l+00 0.00t+00 0.00tt00 0.00t+00 0.00ft00 0.00t+00 0.00t+00 Ba 140 'O.00t+00 0.00t+00 0.00I100 0.00t+00 0.00t+00 0,00t+00 0.00I100 0.00t+00 0.00t+00 alt.IAlfiS 0.00t+00 0.00t+00 0.00t*00 0.00t+00 0.00t+00 0.00t+00 0.00t+00 0.00i+00 0.00t+00
7ABLI:9.1.1.b IIACTOi000LAST(uCi/ce) 15070ft 2130 2145 2200 2215 2230 22(5 2300 2315 2330 Er-85s 6.08802 5.69t02 1.87t02 1.78102 1.121-02 1.67802 2.02802 1.!(I-02 1.42802 tr 85 1.91802 1.85802 6.31103 6.31803 6.30103 6.31t-03 6.308-03 6.31103 6.101-03 tr87 3.06t02 2.40I02 1.14803 6.24I03 5.4(I03 4.74803 (.141-03 3.62803 3.05803 tr-88 1.098-01 9.98102 3.35102 3.0lt02 2.83I02 2.67I02 2.51802 2.36802 2.15802 Ie133 3.57t+00 3.46t*00 1.18t+00 1.17t+00 1.17t+00 1.17t+00 1.17t+00 1.17t+00 1.13t+00 Ie135 6.21t01 5.90I01 1.97t01 1.94801 1.90101 1.86t01 1.82801 1.80801 1.71801 TOTALR.G. 4.40t+00 4.25tt00 1.44t+00 1.43t+00 1.42t+00 1.(II+00 1.40t+00 1.40!+00 1.34t+00 1131 6.56t+0! 6.55t+01- 6.55t+01 6.55t+0! 6,54t+01 6.53t+0! 6.53t+01 6.52t+01 6.51t+01 1132 4.59t+00 4.27t+00 3.96t+00 3.67t+00 3.40t+00 3.15t+00 2.92ft00 2.12t+00 2.52tiOO l133 (.24t+01 (.20t+01 4.17D01 4.14t+01 4.09t+0! 4.07t+01 4.03t+01 4.00t+01 3.96tt0! l134 2.11t+00 1.72t+00 1.42t+00 1.16tt00 9.52101 7.61801 6.40E01 5.25t01 (.315Ci 1135 1.9(I+01 1.90t+01 1.85t+01 1.80t+0! 1.76t+01 1.72t+01 1.67t+01 1.63tt01 1.58t+01 TOTAL 10011t 1.3(1402 1.33t+02 1.31t+02 1.30t+02 1.28t+02 1.27t+02 1.268t02 1.25t+02 1.24t+02 Cs134 9.09801 9.09801 9.09t-01 9.08801 9.08t01 9.09801 9.09101 9.09t-01 9.09801 Cs 137 5.63!01 5.631-01 5.63I01 5.62t-01 5.62801 5.62801 5.62t01 5.62101 5.62801 Cs 138 2.09803 1.52803 1.10I03 7.95t-04 5.751-04 4.16t04 3.02804 2.19104 1.59804 ALI.HitALS 1.47t+00 1.(7t+00 1.47t+00 1.47t+00 1.47t+00 1.478400 1.47t+00 1.47t+00 1.47t+00 fe132 0.00It00 0.00t+00 0.00tt00 0.00tt00 0.00tt00 0.00t*00 0.00t+00 0.00t+00 0.00t+00 St 91 0.00t+00 0.00tt00 0.00!*00 0.00t+00 0,00tt00 0.00!t00 0.00ft00 0.00tt00 0.00tt00 St92 0.00t+00 0.00tt00 0.00t+00 0.00t+00 0.00t+00 0.00tt00 0.00t+00 0.00t+00 0.00t+00 h-140 0.00t+00 0.00t+00 0.00t+00 0.00t+00 0.00ft00 0.00t+00 0.00t+00 0.00t+00 0.00t+00 ALI. IAlfES 0.00ft00 0.00t+00 0.00!+00 0.00!*00 0.00t+00 0.00t+00 0.00t+00 0.00t+00 0.00tt00
y 71BLE:9.1.2.a DifWILL1750STEEFI(uci/cel IS070ft 1800 1930 1945 2000 2015 2030 2045 2100 2115 Ir85 1.621-08 1.62E08 1.56E08 1.501-08 1.45508 1.388-08 1.3(I08 1.28t08 1.24E 08 tr85 3.751-09 3.75t09 3.72I09 3.69509 3.75t09 3.70I-09 3.72109 3.12809 3.12809 tr87 1.651-08 1.651-08 1.43t08 1.25t08 1.10808 S.50t09 8.34t-09 7.271-09 6.358-09 tr-88 3,488-08 3.488-08 3.28t08 3.08508 2.90108 2.71108 2.56t06 2.411-08 2.27808 le133 7.0(I-07 7.04t47 7.03107 7.02107 7.018-07 6.96t07 6.99t-07 6.988-07 6.97807 Ie135 1.45107 1.(5t07 1.381-07 1.36807 1.33t07 1.30807 1.28807 1.25E 07 1.241-01 70741,8.0. 9.15807 9.15t07- 9.08t07 8.998-07 8.92t-07 8.79807 8.78t-07 8.71107 8.66t07 ! l131 3.66808 3.66808 3.668-08 3.65108 3.66t08 3.63108 3.6(E-08 3.65I-08 3.64108 I132 4.65109 (.651-09 4.31t09 4.00109 '3.71809 3((I09 3.19t 09 2.978 09 2.751-09 l133 2.51t08 2.511-08 2.49808 2.47t06 2.45t08 2.43t08 2.(!!06 2.39t-06 2.371-08 1-134 5.68t09 5.68809 4.66t-09 3.82109 2.561-09 2.41t09 2.118 09 1.7(I09 1.(21-09 , 1135 1.33108 1.331-08 1.30808 1.27t08 1.23808 1.20108 1.17108 1.14t08 1!!!08 1 TOTAL 10 DINE 8.54108 8.54808 8.34t08 8.17808 8.028-08 7.88808 7.75t08 7.64808 7.54E08 1 i
fiBLI:9.1.2.b DifWILL ATMOSFElit (uCi/ce) IS0f0ft 2130 2145 2200 2215 2230 2245 2300 2315 2330 Ir 85: 1.191-08 1.14!08 1.10108 1.05808 1.018-08 9.84109 1.19808 9.07809 8.691-09 tr-85 3.72109 3.72t09 3.12109 3.721-09 3.72109 3.73t09 3.128-09 3.73I09 3.721-09 tr-87 5.91809 4.838-09 4.22t09 3.688-09 3.!!!-09 2.80809 2.44t09 2.14I09 1.86t09 1r-88 2.13108 2.01808 1.98808 1.78108 1.61!08 1.58106 1.48t08 1.39t06 1.31108 Ie133 6.96101 6.95101 6.948-01 6.93807 6.92t07 6.92t01 6.90801 6.89807 6.891-01 te 135 1.21t07 1.19t-07 1.16101 1.15tOf 1.12t 07 1.10E-07 1.08I07 1.06t07 1.04801 TOTALN.G. 8.59101 8.54t07 8.48101 8.43507 8.38101 8.34t01 8.28t07 8.24t07 8.20101 1131 3.64108 3.63106 3.63808 3.63t08 3.63108 3.62t08 3.62806 3.61808 3.618-08 I132 2.54t09 2.3ft09 2.19809 2.03t09 1.89t09 1.75809 1.62809 1.51809 1.40E09 I-133 2.35t08 2.33106 2.31808 2.29808 2.!ft08 2.!5108 2.23108 2.!!!08 2.20108 I134 1.17109 9.56t10 f.85I10 6.44I10 5.28I10 4.33I10 3.55810 2.91110 2.39t10 1-135 1.08106 1.05108 1.02I08 1.00108 9.15t-09 9.51t09 9.288-09 9.05t09 8.fft09 TOTAL 10 Dill 7.44806 1.35108 7.21808 7.19108 1.11108 f.05808 6.98808 6.91t08 6.85t-08 1 1 l i 1 l
!!BLt:9.1.3.a 70 TBS LIQUID (uC1/cci 15070ft 1600 1930 1945 2000 2015 2030 20(5 2100 2115 tr85: 8.858-07 2.92806 4.50t 06 6.93t06 1.01805 1.631 05 2.52t-05 3.86805 5.98805 tr85 2.05807 6.778-07 1.07806 1.70806 2.76t-06 4.37806 f.04806 1.12105 1.80805 tr-87 9.00t01 2.971-06 4.148-06 5.11t06 8.09506 1.12105 1.58805 2.19t05 3.07t05 tr-88 1.90806 6,218-06 9.(5t06 1,42105 2.14t05 3.20E05 4.85I05 f.28105 1.10104 le133 3.84105 1.27t-04 2.03t04 3.24104 5.11804 8.!!I-0( 1.32803 2.10803 3.371-03 le135 7.95106 2.62805 3.98t05 6.26t05- 9.81105 1.54804 2.4!t04 3.18t04 5.98t04 70fALI.G. 5.00t05 1.65104 2.62804 (.151-04 6.58104 1.0(I03 1.66803 2.63t03 (.18803 1131 1.84t-06 6.09t05 9.74105 1.56t04 2.49504 3.9810( 6.36t04 1.02803 1.62103 1-132 2.34107 f.f(I06 1.15805 1.71105 2.53t05 3.76805 5.57105 8.26805 1.23104 l133 1.26806 4.17105 6.618-05 1.05t04 1.6ft0( 2.655-04 (.!!I04 6.6ft04 1.061-03 1134 2.86t07 9.44806 1.24105 1.63t05 1.74I05 2.63I05 3.68105 4.84I05 6.32105 I135 6.71107 2.22805 3.465-05 5.40t05 8.42t05 1.311 04 2.04804 3.118 04 4.95104 70fAL10D!ll 4.30t06 1.(28-04 2.2210( 3.48t0( 5.46t04 8.59804 1.35t03 2.13803 3.368-03 Cs134 0.00ft00 3.88806 6.17106 7.(OI06 8.90806 1.07805 1.33I05 1.55805 1.86105 Cs137 0.00ft00 2.GI 06 3.82t-06 4.58106 5.52t06 6.63806 8.26806 9.56t06 1.15t05 Cs 138 0.00ft00 1.18107 1.36t07 1.18801 1.03807 8.97808 8.08808 6.77808 5.90108 Alt.ElfALS 0.00tt00 6.40t06 1.0ll05 1.21t05 1.45t05 1.751-05 2.17105 2.518 05 3.01805 l
l l l l ~. . U
p t TABLI: 9.1.3.b 70E05 LIQUID NCi/ce) t IS070ft 2130 2145 2200 2215 2230 !!(5 2300 2315 2330 Ir85s 9.171-05 1.418-04 1.36804 8.83I03 8.508-03 8.25803 1.00I02 7.60I-03 7.288-03 tr85 2.88805 4.60!05 4.60805 3.12803 3.12t03 3.12803 3.12t03 3.!!!03 3.128-03 tr87 4.62805 5.978-05 5.218-05 3.09t03 2.698-03 2.35803 2.058-03 1.798-03 1.568-03 tr83 1.65804 2.48104 2.4480( 1.498-02 1.408-02 1.328-02 1.!(I02 1.171-02 1.10102 le-133 5.388-03 8.58t-03 8.57t-03 5.818-01 5.808-01 5.80E01 5.78801- 5.78801 5.77801 te135 9.378-04 1.478-03 1.44803 9.618-02 9.415-02 9.22802 9.02102 8.91t-02 8.73E02 707&LI.G. 6.65803 1.05102 1.051-02 7.061-01 7.03801 6.998-01 6.9(I01 6.918-01 6.87I01 1131 2.60I03 4.155-03 4.15803 5.10t-01 5.10E01 5.098-01 5.09t01 5.085-01 5.07t01 1132 1.82804 2.71804 2.518 04 2.86t02 2.65t02 2.(6102 2.27802 2.12802 1.96802 I-133 1.68803 2.66103 2.64103 3.22801 3.19t01 3.17801 3.148 01 3.12801 3.098-01 1134 8.34t-05 1.09104 8.97805 9.04803 7.428-03 6.091-03 4.998-03 (095-03 3.36t-03 1135 7.70I04 1.20103 1.178-03 1.40t01 1.37t-01 1.34t01 1.30t01 1.27t-01 1.23t01 707&L10DIII 5.311-03 8.40E03 8.31E 03 1.0lt+00 1.00t+00 9.90t01 9.808 -01 9.715-01 9.62I01 l Cs134 2.228-05 2.67805 2.67I05 2.22t04 2.22804 2.228-04 2.22804 2.!!I-04 2.22t04
-Cs 137 1.388-05 1.65t05 1.658-05 1.38104 1.381 04 1.385 04 1,38t 01 1.38t04 1.388-04 Cs-138 5.12I08 4.45108 3.22808 1.9(I-07 1.411-07 1.028-07 7.38163 5.36808 3.898-08 alt.IlfALS 3,60104 3.60t-05 4.32t-05 4.32105 3.60104 3.60804 3.60104 3.60804 3.60804
)
1 l l l
1ABI,t:9.1.4.a l 10!DSA7E05 Fit!!(uti/ce) 15070ft 1800 1930 1945 2000 2015 2030 2045 !!00 2115 l 1 l Kr-85: 8.85t08 1.03506 8.161 06 3.321-05 1.28104 4.93t04 9.73t04 1.901-03 3.76103 tr85 2.05t-08 2.39t07 1.94!06 8.!(E06 3.33t05 1.32504 2.711-04 5.53804 1.138-03 tr87 9.00108 1.05!-06 7.498-06 2.76t-05 9.75t05 3.3910( 6.0ft-04 1.08803 1.93t03 i~ tr88 1.90107 2.21t06 1.71805 6.79t05 2.58804 9.68t-04 1.87803 3.59803 '6.89t-03 Ie133 3.841-06 4.48t05 3.671-04 1.55803 6.23I03 2.49t02 5.10802 1.04801 2.128-01 Ie-135- 7,95107 9.25t06 7.21t05 3.00104 1.18103 4.65t03 9.35t03 1.86102 3.16102 107ALN.G. 5.00E06 5.82105 4.7(I-04 1.99803 7.93I03 3.14t02 6.40802 1.29101 2.638 1131 4.291-09 3.831-06 3.061-04 1.29t03 5.44803 2.27102 9.56t02 2.29801 5.50801 1132 5.45t10 -4.871-07 3.61t-05 1.42804 5.52t04 2.15t-03 8.38803 1.86t02 (.16!02 1-133 2.9(I09 2,63t06 2.088-04 8.73t04 3.64103 1.51802 6.338-02 1.50801 3.58t01 1-134 6.65810 5.94t07 3.89105 1.35t04 3.80804 1.50t03 5.53I03 1.09802 2.14802 1135 1.56t09 1.39106 1.09t04 4.48104 1.84t-03 7.46503 3.07802 7.168-02 1.67t01 107AL10DIII 1.00E08 8.93t06 6.98t04 2.89803 1.19102 (.91802 2.03501 4.818-01 1.14t+00
3: fillt: 9.1.(.b TORUS Lit 05ff!FI (uti/ce) IS070ft- 2130 2145 2200 2215 2230 22(5 2300 2315 2330 Ir85e 7.33t03 1.(51-02 9.48E03 9.065-03 8.72t03 8.46103 1.03502 7.80E 03 7.47803 tr85 2.30!03 (.72t03 3.20E03 3.20103 3.20503 3.20t-03 3.20t03 3.!!I03 3,20103 tr87 3.69t03 6.13t-03 3.63t-03 3.17t03 2.76t03 2.(ll03 2.10t03 1.84103 1.60103 tr 88 1.32I02 2.54102 1.70802 1.53802 1(3102 1.3CE02 1.27t-02 1.20E02 1.13t02 le 133 4.30801 8.81801 5.97101 5.96I01 5.95801 5.95101 5.93801 5.93801 5.92t01 le135 7.49t02 1.50101 9.99802 9.86t02 9.66102 9.46t02 9.26102 9.15t02 8.96802 70fil,l.G. 5.31t01 1.08t+00 7.30E01 f25!01 7.21101 f.17101 7.12101 7.09101 f.051-01 1-131 1.32t+00 3.16t+00 4.08t+0! 4.08t+01 (.08t+01 4.07t+01 (.07t+0! 4.06t+01 (.06t+01 1-132 9.20I02 2.06t-01 2.(7t+00 2.29t+00 2.12t+00 1.96t+00 1.82t+00 1.69t+00 1.5ft+00 1133 8.50101 2.03t+00 2.60t+0! 2.58t+01 2.55t+0! 2.53t+01 2.51t+01 2.49t+01 2.47t+01 1134. 4.23102 8.311 02 f.82t-01 7.23101 5.93t01 4.178-01 3.99801 3.27801 2.698-01 3.90I-01 9.14801 1.15t+01 1.12t+01 1.10t+01 1.07t+01 1.04t+01 1.02t+01 9.85t+00 fui&L10DIII 2.69t+00 6.39t+00_ 8.17t+01 8.08t+01 8.00t+01 7.92t+0! 7.8(I+01 7.77t+0! f.10t+01 l l 1 l l
4 .- P SECTION 9.2 RADIATION-AREA DATA 1 l l
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l l
COOPER NUCLEAR STATION TABLE-9.2.1 AREA RADIATION MONI'1DRS (mR/hr) Monitor 1800 1830 1845 1900 1915 1930 1945' Nurber Location
- Ranae 1830 1845 1900 1915 1930 1945 2000 1 Fuel Pool 100-10 6 154 154 154 154 154 154 154 2 Fuel Pool .02-10 2 1.5 1.5 1.5 1.5 1.5 1.5 1.5 3 New Fuel .01-10 2 0.3 0.3 0.3 0.3 0.3 0.3 0.3 4 RWCU Precoat .1-10 3 113 113 113 113 113 113 113 5 RWCU Decant .1-10 3 0.8 0.8 0.8 0.8 0.8 0.8 0.8 6 Tip Rm .1-10 3 164 164 164 164 164 164 164 7 Tip Drives .01-10 2 1.8 1.8 1.8 1.8 1.8 1.8 25 8 CRD S .01-10 0.9 0.9 0.9 0.9 0.9 -
0.9 20 9 CRD N .01-10 2 9 9 9 9 9 9 20' 10 HPCI .01-10 2 0.3/5 5 4 4 3 0.3 4 11 RHR (SW) .01-10 2 5 5 5 5 5 5 40 12 RHR (NW) .01-10 2 24 24 24 24 24 24- 40 2 2 2 2 2 40 13 RCIC/CS (NE) .01-10 2 2 14 CS (SE) .01-10 5 5 5 5 5 5 40 15 Turb. Front Std. .1-10 3 131 131 118 118 118 58 20 16 Turb. MEZZ. .01-10 2 0.2 0.2 0.2 0.2 0.2 0.2 0.2 17 Turb. bsat. C. C. .01-10 2 .05 .05 .05 .05 .05 .05 .05 18 Rx Fd. Pump 1.0-10 4 6 6 6 6 6 6 2 ! 19 Cond. Pump .01-10 2 .12 .12 .12 .12 .12 .12 .12 l 20 Control Rm. .01-10 .02 .02 .02 .02 .02 .02 .02 21 Control Corr .01-10 .19 .19 .19 .19 .19 .19 .19 22 RW Cont. Rm. .01-10 2 .03 .03 .03 .03 .03 .03 .03 23 RW Pump Rm. .01-10 5 5 5 5 5 5 5 24 RW Bsat. .01-10 2 4 4 4 4 4 4 4 25 Demin Viv. Rm. .1-10 3 1.2 1.2 1.2 1.2 1.2 1.2 1.2 3 0.2 0.2 0.2 26 RW Op. Area .1-10 0.2 0.2 0.2 0.2 27 SPARE ----- 28 RW Lab .01-10 2 .01 .01 .01 .01 .01 .01 .01 29 Centrifuge E. .01-10 3 10 10 10 10 10 10 10 30 Centrifuge W. .01-10 3 9 9 9 9 9 9 9 TB = Turbine Building; RB = Reactor Building; RW = Radwaste Building; OSH = Offscale High i
COOPER NUCLEAR STATION ~, TABLE 9.2.1 (cont.) AREA RADIATION MONITORS (mR/hr) Monitor 2000 2015 2030 2045 2100 2115 2130 Number Location , Rance 2015 2030 2045 2100 2115 2130 2145 1 Fuel Pool 100-10.6 154 154 154 154 154- 154 154 2 1.5 1.5 1.5 1.5 1.5 2 Fuel Pool .02-10 1.5 1.5 , 3 New Fuel .01-10 2 0.3 0.3 0.3 0.3 0.3 0.3 0.3 4 RWCU Precoat .1-10 3 113 113 113 113 113 113 113 5 RWCU Decant .1-10 3 0.8 0.8 0.8 0.8 0.8 0.8 0.8 6 Tip Rm .1-10 3 164 164 164 164 164 164 164 7 Tip Drives .01-10 18 17 13 10 8 2 1.8 8 CRD S .01-10 2 13 12 9 6 7 1 0.9 9 CRD N .01-10 2 13 12 9 9 9 9 9 10 HPCI .01-10 2 6 6 7 7 8 8 12 11 RHR (SW) .01-10 2 60 70 70 80 80 120 250 12 RHR (NW) .01-10 60 70 70 80 80 120 250 13 RCIC/CS (NE) .01-10 60 70 70 80 80 120 250 14 CS (SE) .01-10 2 60 70 70 80 80 120 250 15 Turb. Front Std. .1-10 3 2 1 1 1 1 1 1 t 16 Turb. MEZZ. .01-10 2 0.2 0.2 0.2 0.2 0.2 0.2 0.2 17 Turb. bsat. C. C. .01-10 2 .05 .05 .05 .05 .05 .05 .05 18 Rx Fd. Pump 1.0-10 4 1 1 1 1 1 1 1 19 Cond. Pump .01-10 .12 .12 .12 .12 .12 .12 .12 20 Control Rm. .01-10 .02 .02 .02 .02 .02 .02 .02 21 Control Corr .01-10 2 .19 .19 .19 .19 .19 .19 .19 22 RW Cont. Ra. .01-10 .03 .03 .03 .03 .03 .03 .03 23 RW Pump Rs. .01-10 2 5 5 5 5 5 5 5 , 24 RW Bsat. .01-10 4 4 4 4 4 4 4 ; 25 Demin Viv. Rm. .1-10 3 1.2 1.2 1.2 1.2 1.2 1.2 1.2 ' 26 RW Op. Area .1-10 3 0.2 0.2 0.2 0.2 0.2 0.2 0.2 27 SPARE ----- 2 28 RW Lab .01-10 .01 .01 .01 .01 .01 .01 .01 29 Centrifuge E. .01-10 3 10 10 10 10 10 10 10, ' 30 Centrifuge W. .01-10 3 9 9 9 9 9 9 9 TB = Turbine Building; RB = Reactor Building; RW = Radwaste Building; OSH = Offscale High
COOPER NUCLEAR STATION TABLE 9.2.1 (cont.) AREA RADIATION MONITORS fmR/hr) Monitor 2145 2200 2215 2230 Nurber Location
- Ranae 2200 2215 2230 2245 1 Fuel Pool 100-10 6 154 154 154 154 2 Fuel Pool .02-10 2 1.5 1.5 1.5 1.5 3 New Fuel .01-10 2 0.3 0.3 0.3 0.3 4 RWCU Precoat .1-10 3 113 113 113 113 5 RWCU Decant .1-10 3 0.8 0. tt 0.8 0.8 6 Tip Rm .1-10 3 164 164 164 164 7 Tip Drives .01-10 2 1.8 1.8 1.8 1.8 8 CRD S .01-10 0.9 0.9 0.9 0.9 9 CRD N .01-10 2 9 9 9 9 10 HPCI .01-10 2 25 25 25 25 11 RHR (SW) .01-10 2 250 250 250 250 12 RHR (NW) .01-10 250 250 250 250 13 RCIC/CS (NE) .01-10 2 250 250 250 250 14 CS (SE) .01-10 2 250 250 250 250 15 Turb. Front Std. .1-10 3 y y y y 16 Turb. MEZZ. .01-10 2 0.2 0.2 0.2 0.2 17 Turb. bsmt. C. C. .01-10 2 .05 .05 .05 .05 '
18 Rx Fd. Pump 1.0-10 4 1 1 1 1 19 Cond. Pump .01-10 2 .12 .12 .12 .12 20 Control Rm. .01-10 2 .02 .02 .02 .02 21 Control Corr .01-10 2 .19 .19 .19 .19 22 RW Cont. Rm. .01-10 2 .03 .03 .03 .03 23 RW Pump Rm. .01-10 2 5 5 5 5 24 RW Bsat. .01-10 4 4 4 4 3 25 Demin Viv. Rm. .1-10 1.2 1.2 1.2 1.2 26 RW Op. Area .1-10 3 0.2 0.2 0.2 0.2 27 SPARE ----- 28 RW Lab .01-10 2 .01 .01 .01 .01 29 Centrifuge E. .01-10 3 10 10 10 10 30 Centrifuge W. .01-10 3 9 9 9 9 TB = Turbine Building; RB = Reactor Building; RW = Radwaste Building; OSH = Offscale High
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inat2 9.2.14 Assamme e soltates ss. 98r 1900 1830 1943 1900 1915 1930 1945 2000 2015 2030 2043 2100 2113 2130 214S 2200 2215 2230 224S 0 18J3,0, 1845 M M M M M 2015 E M M M M M M M M 2243 M Ambient Radiation 1.evel (mRlhr) 2en. A As Reed ------------ ~------- - - - - - - - - - ~ - - 1900 1850 1780 1050 925 FSO 700 650 650 650 Nota Dove levels less than 2.0 edihr not detectable on PO2A (PD) Cont amination 1.evels (dom ocr 100 cm') Ceners! Areas As Reed ----------- -- - - -
-- =4------- 10E 12K 158C 18E 1*K 19E 19K 19E 1st 19K Airborne Radioactivity Level (uC1fec)
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Taas a 0.2.15 UWTSIDE AMERS 1900 1930 1945 1900 1915 1930 1945 2000 2015 2030 2045 2100 2115 2130 2165 2200 2215 2230 2245 IE2E lE'1 1920 3211 11},Q 1211 22gg 2111 gg,}g J,0,11 2121 {111 {1,22 glil gggg JJ,,1} 32,22 3231 g})g Ambient Radiation Lew! teR/br) Zone A As Reed ---------- ~ ----- - - - - - - ~ ' ~ 230 230 215 40 10 3 - - - - - - - - - - - - ~ ~ - - - - - - - - - - - - Zone 8 As Read ------- ~~ - - -
-~ -------------- 30 70 65 12 3 ~ ~ - - - - - - - - - - - - ~ - - - - - - -
Zone C As Reed --- - - - - ----- -- 25 23 21 4 2 - - - - - - - ~ ~ - - - - - ~ - - - - ~ ~ ~ - Zone D AS Reed --------- 40 35 30 5 2 BRCD - - - - - - -- ---- ------- ~--- Zone E A Reed --- --- ~ - - to le 6 2 FRCD -
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Netoe Dese 1ewis lose then 2.0 eAthr not detectable en RO2A (RD) Cent aminst ten 1..wIs (dem per 100 car') General Areas See Onsite Fleid date Airborne Radioactivit? Lew1 (ese) General Areas See Onsite Field data
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I i t i i i t i 4 i SECTION 10.0 METEOROLOGICAL AND RADIOLOGICAL RELEASE DATA 3 F k I I I f I . - . - .- -. . . .
i e
10.0 INTRODUCTION
This section provides the information necessary for participants to evaluate the magnitude of the radioactive release and to respond appropriately. The postulated fuel damage occurs as a result undampened power oscillations caused by an immediate loss of the recirculation pumps without coastdown. Containment isolation is successful, except for the AOG Steam Supply Isolation Valves MO-920 and MO-921 vhich f ail to close. A release path is established out of the AOG to the Elevated Release Point. This is an elevated and monitored release. Subsecruently, a steam jet air ejector steam supply line ruptures in the ARW building. ARW ventilation picks up this contaminated steam and dischargen it to the environment via the ARW Building Ventilation. The release is then considered a ground level, unfiltered, monitored release. Section 10 furnishes scenario controllers the specific data ' necessary for providing participants the information that simulates the radiochemical and environmental conditions of the postulated event. Section 10.1 includes a figure which shows the release rate ' curve. Section 10.2 gives meteorological data and the current weather forecast. Section 10.3 gives readings and results within the site boundary. Section 10.4 contains the same information as 10.3 but for the areas outside the site boundary up to the 10 mile EPZ. Section 10.5 pictorially displays the geographic path of the plume. I l I l
i SECTION 10.1 RADIOACTIVE RELEASE INFORMATION
,.a ., , a s a.+wg .
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I r I r l t SECTION 10.2 METEOROLOGICAL DATA
i TABLE 10.2.1 , METEOROLOGICAL DATA (PRIMARY SENSORS, 100-10 METER SENSORS) TIME SPEED DIRECTION DELTA-T
. __ b. (
1800 5.0 191 -1.4 1815 7.0 191 -1.3 1830 6.5 193 -1.4 1845 8.0 192 -1.5 1900 7.0 190 -1.3 1915 4 5 193 -1.4 1930 6.0 192 -1.4 1945 4.0 191 -1.4 2000 5.0 191 -1.4 2015 5.0 192 -1.5 2030 4.0 190 -1.4 2045 5.0 191 -1.4 2100 6.0 192 -1.4 2115 8.0 190 -1.5 2130 10.0 192 -1.6 2145 12.0 192 -1.6 2200 12.0 191 -1.6 2215 13.0 192 -1.7 2230 15.5 193 -1.7 , 2245 15.0 193 -1.8 2300 14.5 194 -1.7 l 1 l 1
I i l l l TABLE 10.2.2 l i KETEOROLOGIchL FORECAST j j Evening: Skies will be partly cloudy this evening, with winds , out of the south. Winds of 5 to 15 mph are expected 1 with gusts of up to 20 mph. Cool temperatures will persist with a less than a lot chance of rain. Morning: Expect partly cloudy skies tomorrow morning with light winds out of the south. Temneratures will be seasonably cool, in the middle to' upper 50's, with winds 5 to 10 mph. Afternoon: Clear and seasonably <ool with temperatures in the mid 60's. Clouds developing later with winds increasing 15-20 mph from the south. An increased ' chance of precipitation of 50% towards evening.
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t l t f I i SECTION 10.3 ; ON8ITE FIELD DATA
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r TABLE: 10.3.1 ON-SITE WHOLE BODY DCSE RATES
; CLOSED WINDOW READINGS (mR/hr)
DOWNWIND DISTANCE (meters) TIME 200 400 600 800 1000 1200 1930 1945 10 7 4 3 1 0.5 2000 10 7. 4 3 1 0.5 2015 ' 6 4 2 1 0.6 0.3 ( - 2030 25 21 19 17 15 11 2045 23 19 li 15 13 9 2100 21 17 15 13 11 7.5 2115 4 2 1 0.5 * *
'2130 * * * * *
- 9 ALL VALUES ARE CALCULATED AT PLUME CENTERLINE.
9 FOR MEASUREMENTS ~TAKEN OFF-CENTERLINE, INTERPOLATE BETWEEN THE CENTERLINE AND THE EDGE OF THE PLUME. ASSUME VALUE AT PLUME EDGE EQUALS 10% OF CENTERLINE. 9 BACKGROUND LEVELS (LESS THAN .02 mR/hr) ARE INDICATED BY
- 1
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' TABLE: 10,3,2 ON-SITE WHOLE BODY DOSE RATES OPEN WINDOW READINGS (mR/hr)
DOWNWIND DISTANCE (meters) TIME 200 400 600 800 1000 1200 1930 1945 23 16 9 7 2 1 2000 23 16 9 7 2 1 2015., 14 9 4 2 1 0.7 2030 58 48 14 4 39 35 25 > 2045 53 44 39 35 30 21 2100 48 39 35 30 25 17 2115 '9 4 2 1 *
- 2130 2
- l 0 ALL VALUES ARE . CALCULATED AT PLUME CENTERLINE.
9 FOR MEASUREMENTS TAKEN OFF-CENTERLINE, INTERPOLATE BETWEEN THE CENTERLINE AND THE EDGE OF THE PIEME. ASSUME VALUE AT PLUME EDGE EQUALS 10% OF CENTERLINE. O BACKGROUND LEVELS (LESS THAN .02-mR/hr) ARE INDICATED BY *
[. s L f. TABLE: 10.3.3 ON-SITE CHILD THYROID DOSE RATES (mR/hr) DOWNWIND DISTANCE (meters) TIME 200 400 600 800 1000 1200 1930 1945 2000 2015, 2030 2.7E4 2.3E4 1.9E4 1.5E4 1.3E4 1.2E4 2045 2.5E4 2.lE4 1.7E4 1.3E4 1.2E4 1.lE4 2100 1.9E4 1.6E4 1.lE4 9.8E3 8.7E3 8.2E3 2115 2130 0 ALL VALUES ARE CALCULATED AT PLUME CENTERLINE. O FOR MEASUREMENTS TAKEN OFF-CENTERLINE, INTERPOLATE BETWEEN THE CENTERLINE AND THE EDGE OF THE PLUME. ASSUME VALUE AT PLUME EDGE EQUALS 10% OF CENTERLINE. O BACKGROUND LEVELS (LESS THAN .02 mR/hr) ARE INDICATED BY
- 7-I 1
t TABLE: 10.3.4 ON-SITE CARTRIDGE DATA l E-140-N (177c probc) OR RO-2 READINGS (mR/hr) DOWNWIND DISTANCE (meters) TIME 200 400 600 800 1000 1200 4 1930 1945 2000 2015, 2030 11 9 13 6 5 5 2045 10 9 7 5 4 4 2100 8. 7 5 4 3 3 2115 2130 0 ALL VALUES ARE CALCULATED AT PLUME CENTERLINE. O FOR MEASUREMENTS TAKEN OFF-CENTERLINE, INTERPOLATE BETWEEN THE CENTERLINE AND THE EDGE OF THE PLUME. ASSUME VALUE AT PLUME EDGE EQUALS 10% OF CENTERLINE. O BACKGROUND LEVELS (LESS THAN .02 mR/hr) ARE INDICATED BY
- 1--
TABLE: 10.3.5 ON-SITE CARTRIDGE DATA SAM-2 READINGS (CPM) DOWNWIND DISTANCE (meters) TIME 200 400 600 800 1000 1200 1930 ! 1945 < 2000 * * * * *
- 2015, * * * * *
- 4 2030 2.2E5 1.9ES 1.6E5 1.2E5 1.1E5 9.9E4 2045 2.lES 1.7ES 1.4E5 1.lES 9.9E4 9.lE4 2100 1.6ES 1.3E5 9.lE4 8.lE4 7.2E4 6.8E4 2115 * * * * *
- 2130 i
0 ALL VALUES ARE CALCULATED AT PLUME CENTERLINE. O FOR MEASUREMENTS TAKEN OFF-CENTERLINE, INTERPOLATE BETWEEN THE CENTERLINE AND THE EDGE OF THE PLUME. ASSUME VALUE AT PLUME EDGE EQUALS 10% OF CENTERLINE. O BACKGROUND LEVELS (LESS THAN .02 mR/hr) ARE INDICATED BY
- h t
I- ' q. t 9 SECTIO 10. 4 OFFSITE FIELD DATA
Yasta 1o.4.1 m POSITIc5 DOWmtIND DISTANCE (miles) TIME 5.5. 1.5 2.0 2.5 3.0 3.5 4.0 4.5 5.0 3.5 6.0 6.5 7.0 7.5 8.0 8.5 9.0 9.5 10.0 1945 2000 XXXX 2015 XXXX XXXX XXXX 2030 XXXX XXXX XXXX XXXX XXXX XXXX 2045 XXXX XXXX XXXX XXXX XXXX XXXX XXXX XXXX 2100 XXXX XXXK XXXX XXXX XXXX XXXX XXXX XXXX XXXX XXXX XXXX 2115 XXXX XXXX XXXX XXXX XXXX XXXX XXXX XXXX XXXX XXXX XXXX XXXX XXXX XXXK 2130 XXXX XXXX XXXX XXXX XXXX XXXX XXXX XXXK XXXX XXXX XXXX XXXX XXXX XXXX XXXX XXXX XXXX XXXX XXXX 2145 XXXX XXXX XXXX XXXX XXXX XXXX XXXX XXXK KXXK XXXK XXXX XXXX XXXX XXXX XXXX 2200 ZXXX XXXX XXXX XXXX XXXX XXXX XXXX XXXX XXXK 2215 XXXX XXXX XXXK 1 i I l
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.J-TABER 10.4.3 CIDSED WIMtOIf UNDR2 BOOT DOSE RATES (aR/hr)
DOWNWIND DISTAf1CE (miles) TIME S.B. 1.5 2.0 2.5 3.0 3.5 4.0 4.5 5.0 5.5 6.0 6.5 7.0 7.5 8.0 8.5 9.0 9.5 10.0 1945 2000 0.2 2015 0.2 0.1 0.1 2030 0.1 0.1 0.1 0.1 0.1 *** 2045 5.5 0.1 *** *** *** *** *** 2100 4.0 3.5 1.7 1.2 *** *** *** *** 2115 3.0 2.0 0.9 0.8 0.6 0.8 0.6 *** *** 2130 0.6 0.5 0.4 0.3 0.2 0.3 0.2 0.2 0.2 0.1 0.1 0.2 0.1 0.1 0.1 0.1 *** *** 2145
*** 0.1 0.1 0.1 0.1 2200
= *** ***
2215 INT
- DOSE 3.3E+00 1.4E+00 6.9E-01 7.0E-01 3.4E-01 3.4E-01 2.6E-01 9.5E-02 6.6E-02 1.1E-01 1.0E-01 9.0E-02 4.4E-02 3.9E-02 4.4E-02 5.2E-02 4.8E-02 2.1E-02 2.0E-02 MAX
- ICSE 2.2E+01 1.4E+01 6.9E+00 5.3E+00 4.5E+00 3.8E+00 3.1E+00 2.3E+00 1.6E+00 1.5E+00 1.4E+00 1.2E+00 1.1E+00 1.0E+00 8.8E-01 7.6E-01 6.4E-01 5.2E-01 4.0E-01
- INT Dose is the actual dose recetwed if esposed at centerline for the entire release.
**MAK Dose is the projected dose based on the def ault duration for centerline values. *** baekaround Notes:
- 1) All values represent plume centerline readings
- 2) For measuremens taken off-centerline, interpolate between the centerline value and the edge of the plume.
- 3) The value at the plume edge equals 11 of the centerline readings.
. ~ . - - -~
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T4312 10.4.4 OPER IflMictf WIMLE SMFY DOSE RATE (apfhr) DOWNWIND DISTANCE (miles) TIME S.B. 1.5 2.0 2.5 ?O 3.5 4.0 4.5 5.0 5.5 6.0 6.5 7.0 7.5 8.0 8.5 9.0 9.5 10.0 1945 2000 0.5 2015 0.5 0.3 0.2 2030 0.2 0.3 0.1 0.1 0.1 0.1 2045 13 0.2 0.1 0.1 0.1 0.1 0.1 0.1 2100 9.2 8.1 3.9 2.8 0.1 0.1 0.1 2115 6.9 4.5 2.0 1.8 1.5 1.7 1.4 *** *** ***
*** 0.9 0.5 0.6 0.6 0.5 ***
2130 1.6 1.3 1.2 0.7
*** O.3 0.3 0.3 0.3 0.3 0.3 0.3 0.2 ***
2145
*** 0.1 0.2 0.2 0.2 0.1 2200 2215 l
i Notes:
- 1) All values represent plume centerline readines.
( 2) For measurements taken off-centerline, interpolate between the centerline value and the edge of the plume.
- 3) The value at the plume edge equais 15 of the centerline readines.
*** baekaround l
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f ( TAsoE 18.4.5 GIIA TNTROID DOSE RATES (edtsunthr) DOWNWIttD DISTANCE (miles) 7.0 7.5 8.0 8.5 9.0 9.5 10.0 4.0 4.5 5.0 5.5 6.0 6.5 1.5 2.0 2.5 3.0 3.5 TIME S.B. 1945 2000 260 2015 200 180 110 190 140 79 87 75 63 2030 68 69 59 51 49 36 2045 7203 120 49 41 39 30 26 22 21 2100 6600 4600 2300 1700 15 18 17 15 17 15 1700 1500 1200 1000 820 22 2115 5100 3300 310 2 90 10 9.2 11 9.8 10 9.3 8.1 980 840 640 540 350 330 2130 1200 220 230 210 1 90 180 160 5.3 4.6 260 240 2145 78 140 130 110 110 2200 2215 INT
- DOSE 4.9E+03 2.1E+03 1.1E+03 1.1E+03 6.0E+02 5.1E+02 3.9E+02 1.6E+02 9.7E+01 1.6E+02 1.5E+02 1.3E+02 6.5E+01 5.9E+01 7.0E+01 8.2E+
puut* DOSE 2.9E+04 1.9E+04 8.4E+03 7.3E+03 6.3E+03 5.2E+03 4.1E+03 3.1E+03 2.0E+03 1.9E+03 1.8E+03 1.6E+03 1.5E+03 1.4E+03 1.3E+03
- INT Dose is the actual dose received if esposed at centerline for the entire release.
**ttAX Dose is the projected dose based on the def ault duration for centerline values.
Eetes:
- 1) All values represent plume centeritne readings
- 2) For measuremens taken off-centerline, interpointe between the centerline value and the edge of the plume.
- 3) The value at the plume edge equals !! of the centerline readings.
TA8t2 10.4.6 IGD 15E CDBCENTRATION IS eCilec DOWWWIND DISTANCE (miles) TIME 5.B. 1.5 2.0 2.5 3.0 3.5 4.0 4.5 5.0 5.5 6.0 6.5 7.0 7.5 8.0 8.5 9.0 9.5 10.0 1045 2000 6.7E-07 2015 5.2E-07 4.6E-07 2.8E-07 2030 4.9E-07 3.7E-07 2.0E-07 2.2E-07 1.9E-07 1.6E-07 2045 1.9E-05 3.0E-07 1.8E-07 1.8E-07 1.5E-07 1.3E-07 1.3E-07 9.4E-08 2100 1.7E-05 1.2E-05 6.1E-06 4.4E-06 1.3E-07 1.1E-07 1.0E-07 7.7E-08 6.7E-08 5.8E-08 5.4E-08 2115 1.3E-05 8.5E-06 4.4E-06 3.8E-06 3.2E-06 2.7E-06 2.1E-06 5.8E-08 3.9E-08 4.6E-08 4.3E-08 4.0E-08 4.3E-08 3.SE-08 2130 1.0E-11 1.0E-11 1.0E-11 3.0E-06 2.5E-06 2.2E-06 1.7E-06 1.4E-06 8.9E-07 8.5E-07 7.9E-07 7.4E-07 2.6E-08 2.4E-00 2.8E-08 2.5E-08 2.7E-00 2.4E-08 2.1E-08 2145 9.3E-12 9.3E-12 9.3E-12 9.3E-12 9.3E-12 6. 7E-07 6.2E-07 5.8E-07 6.0E-07 5.5E-07 5.0E-07 4.5E-07 4.1E-07 1.4E-08 1.2E-08 2S00 8.7E-12 8.7E-12 8.7E-12 8.7E-12 2.0E-07 3.7E-07 3.3E-07 2.9E-07 2.8E-07 2215 8.4E-12 8 4E-12 8.4E-12 No2es:
- 1) All values represent pitane centerline readin8s.
- 2) For amessurements taken off-centerline, interpolate between the centerline value and the ed 8e of the plisne.
- 3) The value at the plume ed 8 e equals II of the centerline readin8s.
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-l TA812 10.4.s SJWE-2 READIWCS SILTER ISDLITE CARTRIDGE DATA READISCS IN CFM DOWNWIND DISTANCE (miles) 5.5 6.0 6.5 7.0 7.5 s.O 8.5 9.0 9.5 30.0 1.5 2.n 2.5 3.0 3.5 4.0 4.5 5.0 TIME 5.5.
I 1945 2000 2000 2015 1500 1400 840 2030 1500 1100 600 660 570 480 900 520 520 450 390 370 280 2045 5.5E+04 1.3E+04 370 310 300 230 200 170 160 2100 5.0E+04 3.6E+04 1.8E+04 7900 6300 170 110 140 130 120 130 120 2115 3.9E+04 2.5E+04 1.3E+04 1.1E+04 9400 2400 2200 77 70 83 75 80 71 62 8900 7500 6400 4900 4100 2600 2500 2130 2000 1800 1700 1800 1600 1500 1300 1200 41 35 2145 600 1100 980 860 840 2200 2215 Noces:
- 1) All values represent plume centerline readings.
- 2) For measurements taken off-centerline, interpolate between the centerline value and the edge of the pitame.
- 3) The value at the pitume edge equals II of the centerline readings.
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TABLE 10.4.9 51LTER EBOLITE CARTRIDCE th4TA IJELIBt 2218 READINCS EBf CFM DOWNWIND DISTANCE (miles) TIME S.B. 1.5 2.0 2.5 3.0 3.5 4.0 4.5 5.0 5.5 6.0 6.5 7.0 7.5 8.0 8.5 9.0 9.5 10.0 If45 2000 4.0E+04 2015 3.1E+04 2.7E+04 1.7E+04 2030 2.9E+04 2.2E+04 1.2E+04 1.3E+04 1.1E+04 9600 1045 1.1E+06 1.8E+04 1.0E+04 1.0E+04 9000 7800 7400 5600 2103 1.0E+06 7.1E+05 3.6E+05 2.6E+05 7500 6300 6000 4600 3900 3400 3200 2115 7.8E+05 5.0E+05 2.6E+05 2. 3E+05 1.9E+05 1.6E+05 1. 3E+05 3400 2300 2700 2500 2400 2500 2300 2150 1.8E+05 1.5E+05 1.3E+05 9.8E+04 8.2E+04 5.3E+04 5.0E+04 4.7E+04 4.4E+04 1500 1400 1700 1500 1600 1400 1200 2145 4.0E+04 3.7E+04 3.4E+04 3.6E+04 3.2E+04 2.9E+04 2.7E+04 2.4E+04 820 710 2200 1.2E+04 2.2E+04 2.0E+04 1.7E+04 1.7E+04 2215 Rotes:
- 1) All values represent pitsee centerline readings.
- 2) For measurements taken off-centerline, interpolate between the centerline value and the edge of the p1tene.
- 3) The value at the pitsee edge equals 12 of the centerline readings.
TABt2 19.4.10 AN SAMLE FILTist DATA E-140-Wfe-219 FRDBE READI M IN CPM DOWININD DISTANCE (miles) TIME S.B. 1.5 2.0 2.5 3.0 3.5 4.0 4.5 5.0 5.5 6.0 6.5 7.0 7.5 8.0 8.5 9.0 9.5 10.0 1945 2000 22 2015 17 15 2030 16 12 2045 e20 10 2100 570 400 200 150 2115 440 280 150 130 110 89 70 2130 100 84 72 55 46 30 28 26 25 2145 22 21 19 29 18 17 15 13 2200 12 11 2215 Y,otes:
- 1) All values represent p1.ume centerline readings.
- 2) For measurements taken off-centerline, interpolate between the centerline value and the edge of the pitume.
- 3) The value at the pitume edge equals 11 of the centerline readinsa.
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